80_FR_12117 80 FR 12073 - List of Approved Spent Fuel Storage Casks: Holtec International HI-STORM Underground Maximum Capacity Canister Storage System, Certificate of Compliance No. 1040

80 FR 12073 - List of Approved Spent Fuel Storage Casks: Holtec International HI-STORM Underground Maximum Capacity Canister Storage System, Certificate of Compliance No. 1040

NUCLEAR REGULATORY COMMISSION

Federal Register Volume 80, Issue 44 (March 6, 2015)

Page Range12073-12078
FR Document2015-05238

The U.S. Nuclear Regulatory Commission (NRC) is amending its spent fuel storage regulations by adding the Holtec International HI- STORM Underground Maximum Capacity (UMAX) Canister Storage System, Certificate of Compliance (CoC) No. 1040, to the ``List of approved spent fuel storage casks.'' Holtec International's intent with this design is to provide an underground storage option compatible with the Holtec International HI-STORM FLOOD/WIND (FW) System (CoC No. 1032).

Federal Register, Volume 80 Issue 44 (Friday, March 6, 2015)
[Federal Register Volume 80, Number 44 (Friday, March 6, 2015)]
[Rules and Regulations]
[Pages 12073-12078]
From the Federal Register Online  [www.thefederalregister.org]
[FR Doc No: 2015-05238]



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Federal Register / Vol. 80, No. 44 / Friday, March 6, 2015 / Rules 
and Regulations

[[Page 12073]]



NUCLEAR REGULATORY COMMISSION

10 CFR Part 72

[NRC-2014-0120]
RIN 3150-AJ42


List of Approved Spent Fuel Storage Casks: Holtec International 
HI-STORM Underground Maximum Capacity Canister Storage System, 
Certificate of Compliance No. 1040

AGENCY: Nuclear Regulatory Commission.

ACTION: Final rule.

-----------------------------------------------------------------------

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is amending its 
spent fuel storage regulations by adding the Holtec International HI-
STORM Underground Maximum Capacity (UMAX) Canister Storage System, 
Certificate of Compliance (CoC) No. 1040, to the ``List of approved 
spent fuel storage casks.'' Holtec International's intent with this 
design is to provide an underground storage option compatible with the 
Holtec International HI-STORM FLOOD/WIND (FW) System (CoC No. 1032).

DATES: This final rule is effective on April 6, 2015.

ADDRESSES: Please refer to Docket ID NRC-2014-0120 when contacting the 
NRC about the availability of information for this action. You may 
obtain publicly-available information related to this action by any of 
the following methods:
     Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2014-0120. Address 
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: Carol.Gallagher@nrc.gov. 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 pdr.resource@nrc.gov. For 
the convenience of the reader, instructions about obtaining materials 
referenced in this document are provided in the ``Availability of 
Documents'' section.
     NRC's PDR: You may examine and purchase copies of public 
documents at the NRC's PDR, Room O-1F21, One White Flint North, 11555 
Rockville Pike, Rockville, Maryland 20852.

FOR FURTHER INFORMATION CONTACT: Gregory R. Trussell, Office of Nuclear 
Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, 
Washington, DC 20555-0001, telephone: 301-415-6445, email: 
Gregory.Trussell@nrc.gov.

SUPPLEMENTARY INFORMATION: 

Table of Contents

I. Background
II. Discussion of Changes
III. Public Comment Analysis
IV. Voluntary Consensus Standards
V. Agreement State Compatibility
VI. Plain Writing
VII. Environmental Assessment and Finding of No Significant 
Environmental Impact
VIII. Paperwork Reduction Act Statement
IX. Regulatory Analysis
X. Regulatory Flexibility Certification
XI. Backfitting and Issue Finality
XII. Congressional Review Act
XIII. Availability of Documents

I. Background

    Section 218(a) of the Nuclear Waste Policy Act (NWPA) of 1982, as 
amended, requires that ``the Secretary [of the Department of Energy] 
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 ``[the Commission] shall, by rule, establish 
procedures for the licensing of any technology approved by the 
Commission under Section 219(a) [sic: 218(a)] for use at the site of 
any civilian nuclear power reactor.''
    To implement this mandate, the Commission approved dry storage of 
spent nuclear fuel in NRC-approved casks under a general license by 
publishing a final rule in part 72 of Title 10 of the Code of Federal 
Regulations (10 CFR), 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 published a direct final rule on this amendment in the 
Federal Register on September 9, 2014 (79 FR 53281). The NRC also 
concurrently published an identical proposed rule on September 9, 2014 
(79 FR 53352). The NRC received at least one comment that is treated as 
a significant adverse comment on the proposed rule; therefore, the NRC 
withdrew the direct final rule on November 19, 2014 (79 FR 68763), and 
is proceeding, in this document, to address the comments on the 
proposed rule (see Section III, Public Comment Analysis, of this 
document).

II. Discussion of Changes

    By letter dated June 29, 2012, and as supplemented on July 16 and 
November 20, 2012; January 30, April 2, April 19, June 21, August 28, 
December 6, and December 31, 2013; and January 13, and January 28, 
2014, Holtec International submitted an application to add the HI-STORM 
UMAX Canister Storage System to the list of approved spent fuel storage 
casks in 10 CFR part 72. The HI-STORM UMAX Canister Storage System is a 
spent fuel storage system designed to be in full compliance with the 
requirements of 10 CFR part 72. Holtec International's intent with this 
design is to provide an underground storage option compatible with the 
Holtec International HI-STORM FW System as described in the Final 
Safety Analysis Report (FSAR) for the HI-STORM FW

[[Page 12074]]

System. The underground structure system is described in the FSAR for 
the HI-STORM UMAX Canister Storage System. The HI-STORM UMAX Canister 
Storage System stores a hermetically sealed canister containing spent 
nuclear fuel (SNF) in an in-ground vertical ventilated module (VVM). 
The HI-STORM UMAX Canister Storage System is designed to provide long-
term underground storage of loaded multi-purpose canisters (MPC) 
previously certified for storage in CoC No. 1032. The HI-STORM UMAX VVM 
is the underground equivalent of the HI-STORM FW storage module. 
Although the storage cavity dimensions and the air ventilation system 
in the HI-STORM UMAX VVM have been selected to enable it to also store 
all MPCs certified for storage in the HI-STORM 100 storage module, CoC 
No. 1040 does not approve the storage of all MPCs certified for storage 
in the HI-STORM 100 storage module in the HI-STORM UMAX VVM at this 
time. The HI-STORM UMAX Canister Storage System can store either 
Pressurized Water Reactor or Boiling Water Reactor fuel assemblies in 
the MPC-37 or MPC-89 models, respectively. The number associated with 
the MPC is the maximum number of fuel assemblies the MPC can contain in 
the fuel basket. The external diameters of the MPC-37 and MPC-89 are 
identical to allow the use of a single storage module design, however 
the height of the MPC, as well as the storage module and transfer cask, 
are variable based on the SNF to be loaded.
    As documented in the safety evaluation report (SER), the NRC staff 
performed a detailed safety evaluation of the proposed CoC request 
submitted by Holtec International.
    The HI-STORM UMAX Canister Storage System, when used under the 
conditions specified in the CoC, the Technical Specifications (TSs), 
and the NRC's regulations, will meet the requirements of 10 CFR part 
72; therefore, adequate protection of public health and safety will 
continue to be ensured. When this final rule becomes effective, persons 
who hold a general license under 10 CFR 72.210 may load spent nuclear 
fuel into HI-STORM UMAX Canister Storage Systems that meet the criteria 
of CoC No. 1040 under 10 CFR 72.212.

III. Public Comment Analysis

    The NRC received multiple comments from private citizens on the 
companion proposed rule to the direct final rule published on September 
9, 2014. The NRC has not made any changes to the proposed rule as a 
result of the public comments the NRC has received.

Summary of Comments

    The NRC received almost a dozen comments on the proposed rule, many 
raising multiple and overlapping issues. Because the NRC received at 
least one comment that it is treating as a significant adverse comment 
on the proposed rule (raising issues the NRC deemed serious enough to 
warrant a substantive response to clarify the record), the NRC withdrew 
the direct final rule and is responding to the comments here. Other 
comments were not treated as significant adverse comments because, in 
most instances, they were beyond the scope of this rulemaking. 
Nonetheless, in addition to responding to the issues raised in the 
comments treated as significant adverse comments, the NRC is also 
taking this opportunity to respond to some of the issues raised in the 
comments that are beyond this scope of this rulemaking in order to 
clarify information about the CoC rulemaking process related to the 
comments received.

Aging Management Programs

    Many of the comments the NRC received questioned the fact that 
aging management programs (AMPs) were not being established for this 
CoC system. Commenters noted that the NRC has not yet issued the 
revision to NUREG-1927 (``Standard Review Plan for Renewal of Spent 
Fuel Dry Cask Storage System Licenses and Certificates of 
Compliance''), which is currently being updated to include information 
regarding AMPs, among other things. The comments stated that the 
approval of this CoC system, ``should be put on hold until after the 
revised NUREG-1927 is final and any appropriate aging management issues 
are addressed in this CoC.''
    The comments questioned some specific example AMPs discussed at 
public meetings, including questions regarding an example AMP for 
Chloride-Induced Stress Corrosion Cracking Tests (seismic concerns and 
sampling size), as well as the absence of an AMP given issues with 
damaged fuels and the ``unknowns of extended storage with high burnup 
fuel.'' In sum, these commenters felt that approval of CoCs, such as 
this one, should await the formulation and approval of aging management 
programs.

Response

    These comments are outside the scope of this rulemaking which is 
limited to amending the spent fuel storage regulations by adding the 
UMAX Canister Storage System, CoC No. 1040, to the ``List of approved 
spent fuel storage casks'' in 10 CFR 72.214. This rulemaking is not 
making any changes to the regulations governing the standards for 
approval of a CoC.
    The CoC for the HI-STORM UMAX is being issued for 20 years in 
accordance with 10 CFR part 72. According to the NRC staff's SER 
published in the Federal Register under Docket ID NRC-2014-0120, the 
staff has determined that the use of the HI-STORM UMAX Canister Storage 
System will be conducted in compliance with the applicable regulations 
of 10 CFR part 72, and the CoC should be approved for the initial 20-
year term. There are currently no technical or regulatory requirements 
for the inclusion of AMPs for the initial 20-year CoC term. AMPs are 
required for spent fuel storage cask renewal which allows storage 
beyond 20 years, as provided in 10 CFR 72.240. The current regulatory 
requirements provide the necessary defense in depth for safe storage of 
spent nuclear fuel for at least 20 years.
    Based on the regulations in 10 CFR part 72, an AMP will be required 
to be included in any renewal application for the HI-STORM UMAX 
Canister Storage System, for a duration beyond the initial 20-year 
term. The renewal application, if filed, will be required to comply 
with the applicable regulations, and consider applicable NRC aging 
management guidance available at the time of submittal. While NUREG-
1927 may prove useful to applicants seeking to renew a CoC, because it 
does not provide guidance regarding applications seeking initial 
approval of certificates, there is no reason to await the guidance 
before proceeding with the addition of this system to the 10 CFR part 
72 regulations.

Inspection Access

    Several comments also questioned the ability of the underground 
storage system to be adequately inspected and potentially repaired if 
necessary during the initial certification period of 20 years, 
especially if the system was being used in a coastal environment where 
stress corrosion cracking could be an issue.

Response

    The NRC is treating this comment as a significant adverse comment 
warranting clarification of the record. The NRC has evaluated the 
design of the HI-STORM UMAX Canister Storage System and has determined 
that the design is robust, and contains numbers of layers of acceptable 
confinement systems in compliance with 10 CFR part

[[Page 12075]]

72 requirements. In addition, the staff is not aware of empirical 
evidence that supports a finding that surveillance would be required in 
the initial certification period of the proposed CoC. This evaluation 
is documented in the NRC staff's SER under Docket ID NRC-2014-0120.
    Furthermore, the NRC has evaluated the susceptibility to and 
effects of stress corrosion cracking and other corrosion mechanisms on 
safety significant systems for SNF dry cask storage (DCS) systems 
during an initial certification period. The staff has determined that 
the HI-STORM UMAX Canister Storage System, when used within the 
requirements of the proposed CoC, will safely store SNF and prevent 
radiation releases and exposure consistent with regulatory 
requirements.

Seismic Protection

    Several comments also raised concerns regarding the ability of this 
CoC system to withstand seismic events, particularly if the system were 
to be used at specific sites with known seismic activity, such as San 
Onofre Nuclear Generating Station (SONGS).

Response

    The NRC is treating this comment as a significant adverse comment 
warranting clarification of the record. This rulemaking would add a CoC 
system to the list of approved spent fuel storage casks in 10 CFR 
72.214. The certification provided by this approval does not, in and of 
itself, authorize use of this system at any specific site. Instead, 
general licensees (a power reactor that stores spent fuel under a 
general Part 72 license) that wish to use this system must first ensure 
that other applicable requirements are met. (See 10 CFR 72.212).
    The seismic design levels of the HI-STORM UMAX Canister Storage 
System as provided in this CoC are acceptable for most areas in the 
continental U.S. For locations that have potential seismic activity 
beyond those analyzed for this system, additional evaluations and 
certifications may be required before the system may be used in those 
locations. The NRC is currently evaluating an amendment request to the 
HI-STORM UMAX Canister Storage System that provides additional analysis 
intended to ensure the system's integrity during an earthquake with 
higher seismic demands, including the seismic demands at the location 
of SONGS. If the NRC approves that amendment request, the amended 
system could be selected for use at SONGS, provided regulatory 
requirements are met.

Bankruptcy

    A comment also raised questions about the implications of the 
potential bankruptcy of corporations that seek CoC approvals.

Response

    This comment is outside the scope of this rulemaking. This 
rulemaking would add a certified system to the list of spent fuel 
systems in 10 CFR 72.214 and does not seek to alter the standards for 
approval of a CoC system. In any event, NRC regulations in 10 CFR part 
72 address the financial viability of licensees to ensure spent fuel 
management and decommissioning are funded. Pursuant to NRC 
requirements, once a general licensee accepts delivery of a storage 
system authorized by a CoC, the financial responsibility for 
maintaining and decommissioning the system become the responsibility of 
the general licensee (see 10 CFR 72.30(b), (c), (d), (e), and (f)).

Flood Protection

    One comment stated that the design basis of the Watts Bar 2 reactor 
(not yet licensed for operation) intends that safe shut down could 
occur if there were a flood event that delivered 13\1/2\ feet of water 
at the reactor buildings. This comment raised the concern that the cask 
waste storage in an adjacent area would have equal or greater flooding.

Response

    This rulemaking is limited to the approval of a CoC system to be 
added to the list of spent fuel storage casks in 10 CFR 72.214. This 
rulemaking does not propose any change to the standards for approval of 
a CoC, or the requirements that govern the use of this CoC by a general 
licensee. Therefore, this comment is outside the scope of this 
rulemaking.
    The NRC's regulations at 10 CFR 72.212, ``Conditions of a general 
license issued under 10 CFR 72.210,'' require that a general licensee 
(a power reactor that stores spent fuel under a general part 72 
license) perform written evaluations to ensure that the DCS systems 
used at the location meet the technical requirements of the CoC. The 
NRC inspects these evaluations prior to the first use of the DCS system 
and every three years after first use to ensure compliance with the 
terms of the CoC. If the CoC does not allow for water intrusion, then 
the general licensee is required to provide engineered measures to 
ensure that this condition does not occur.

High Burnup Fuel

    Several comments also raised questions regarding the long-term 
acceptability of the extended storage of high burnup fuel (HBF).

Response

    Most of the comments raising HBF as an issue did so in the context 
of the need for AMPs for approval of the CoC for the first 20 years, 
and that is beyond the scope of this rulemaking, as explained above.
    To the extent commenters raised issues about the storage of HBF in 
the CoC for the first 20 years, the NRC is treating this portion of the 
comment as a significant adverse comment warranting clarification of 
the record. The NRC has evaluated the acceptability of storage of HBF 
for the initial 20-year certification term for the HI-STORM UMAX 
Canister Storage System. As documented in the NRC staff's SER under 
Docket ID NRC-2014-0120, the staff has determined that the use of the 
HI-STORM UMAX Canister Storage System, including storage of HBF, will 
be conducted in compliance with the applicable regulations of 10 CFR 
part 72, and the CoC should be approved for the initial 20-year term.
    Storage beyond the initial term of 20 years will require the 
applicant to submit a license renewal application with the inclusion of 
AMPs addressing HBF. In that regard, a demonstration project is being 
planned by the U.S. Department of Energy to provide confirmatory data 
on the performance of HBF in DCS. The NRC plans to evaluate the data 
obtained from the project to confirm the accuracy of current models 
that are relied upon for authorizing the storage of HBF for extended 
storage periods beyond the initial 20-year certification term.

Duration of Certificate

    Some comments also raised issues with the limited duration of this 
initial CoC for a term of only 20 years and stated that the systems 
should have to demonstrate safe storage of nuclear fuel for a much 
longer storage period.

Response

    The issues of long-term storage and disposal of SNF are outside the 
scope of this CoC rulemaking. This rule is limited to the addition of 
this storage system to the list of approved designs in 10 CFR 72.214. 
The regulations governing the length of the CoC term are not within the 
changes proposed by this rule.

[[Page 12076]]

Inspector General's Report

    One comment highlighted issues addressed in the 2014 NRC Inspector 
General's report of the SONGS steam generator replacement, entitled, 
``NRC Oversight of Licensee's Use of 10 CFR 50.59 Process to Replace 
SONG'S Steam Generators (Case No. 13-006).''

Response

    The issues raised by the NRC's IG report of the SONGS steam 
generator replacement are outside the scope of this rulemaking. This 
report is applicable only to that proposed steam generator replacement 
effort, and does not apply to nor is it related to this specific CoC 
rulemaking. Approval of this CoC is based upon a safety and 
environmental review of this specific CoC design as submitted by the 
vendor. If power reactor licensees wish to use this system at their 
specific sites, they must first ensure other applicable regulatory 
requirements are met (see 10 CFR 72.212).

IV. 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 final rule, the NRC will add the Holtec 
International HI-STORM UMAX Canister Storage System design to the 
listing in 10 CFR 72.214. This action does not constitute the 
establishment of a standard that contains generally applicable 
requirements.

V. 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 final 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, or the provisions of 10 CFR. 
Although an Agreement State may not adopt program elements reserved to 
the 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.

VI. Plain Writing

    The Plain Writing Act of 2010 (Pub. L. 111-274), requires Federal 
agencies to write documents in a clear, concise, and well-organized 
manner. The NRC has written this document to be consistent with the 
Plain Writing Act as well as the Presidential Memorandum ``Plain 
Language in Government Writing,'' published June 10, 1998 (63 FR 
31883).

VII. Environmental Assessment and Finding of No Significant 
Environmental Impact

A. The Action

    The action is to amend 10 CFR 72.214 to add the Holtec 
International HI-STORM UMAX Canister Storage System to the listing 
within the ``List of approved spent fuel storage casks'' as CoC No. 
1040. Under the National Environmental Policy Act of 1969, as amended, 
and the NRC's regulations in subpart A of 10 CFR part 51, 
``Environmental Protection Regulations for Domestic Licensing and 
Related Regulatory Functions,'' 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. The NRC has made a finding of no 
significant impact on the basis of this environmental assessment.

B. The Need for the Action

    This final rule adds CoC No. 1040 for the Holtec International HI-
STORM UMAX Canister Storage System 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. Specifically, 
Holtec International's intent with this design is to provide an 
underground storage option compatible with the Holtec International HI-
STORM FW System.

C. Environmental Impacts of the Action

    On July 18, 1990 (55 FR 29181), the NRC issued an amendment to 10 
CFR part 72 to provide for the storage of spent fuel under a general 
license in cask designs approved by the NRC. The potential 
environmental impact of using NRC-approved storage casks was initially 
analyzed in the environmental assessment for the 1990 final rule. The 
environmental assessment for this CoC addition tiers off of the 
environmental assessment for the July 18, 1990, final rule. Tiering on 
past environmental assessments is a standard process under the National 
Environmental Policy Act.
    Holtec International HI-STORM UMAX Canister Storage Systems are 
designed to mitigate the effects of design basis accidents that could 
occur during storage. Design basis accidents account for human-induced 
events and the most severe natural phenomena reported for the site and 
surrounding area. Postulated accidents analyzed for an ISFSI, the type 
of facility at which a holder of a power reactor operating license 
would store spent fuel in casks in accordance with 10 CFR part 72, 
include tornado winds and tornado-generated missiles, a design basis 
earthquake, a design basis flood, an accidental cask drop, lightning 
effects, fire, explosions, and other incidents.
    Considering the specific design requirements for each accident 
condition, the design of the HI-STORM UMAX Canister Storage System 
would prevent loss of containment, shielding, and criticality control. 
If there is no loss of containment, shielding, or criticality control, 
the environmental impacts would be insignificant. In addition, any 
resulting occupational exposure or offsite dose rates from the use of 
the HI-STORM UMAX Canister Storage System would remain well within the 
10 CFR part 20 limits. Therefore, the proposed addition of CoC No. 1040 
will not result in radiological or non-radiological environmental 
impacts that significantly differ from the environmental impacts 
evaluated in the environmental assessment supporting the July 18, 1990, 
final rule. There will be no significant change in the types or 
significant revisions in the amounts of effluent released, no 
significant increase in the individual or cumulative radiation 
exposure, and no significant increase in the potential for or 
consequences from radiological accidents. The staff documented its 
safety findings for this review in the SER.

D. Alternative to the Action

    The alternative to this action is to withhold approval of this new 
design and issue a site-specific license to each utility that proposes 
to use the casks. This alternative would cost both the NRC and 
utilities more time and money for each site-specific license. 
Conducting site-specific reviews would ignore the procedures and 
criteria currently in place for the addition of new cask designs that 
can be used under a general license, and would be in conflict with NWPA 
direction to the Commission to approve technologies for the use of 
spent fuel storage at the sites of civilian nuclear power reactors 
without, to the maximum extent practicable, the need for additional 
site reviews. This alternative also would

[[Page 12077]]

tend to exclude new vendors from the business market without cause and 
would arbitrarily limit the choice of cask designs available to power 
reactor licensees. This final rule will eliminate the above problems 
and is consistent with previous Commission actions. Further, the rule 
will have no adverse effect on public health and safety. Therefore, the 
environmental impacts would be the same or less than the action.

E. Alternative Use of Resources

    Approval of the addition of CoC No. 1040 would result in no 
irreversible commitments of resources.

F. Agencies and Persons Contacted

    No agencies or persons outside the NRC were contacted in connection 
with the preparation of this environmental assessment.

G. Finding of No Significant Impact

    The environmental impacts of the action have been reviewed under 
the requirements in 10 CFR part 51. Based on the foregoing 
environmental assessment, the NRC concludes that this final rule 
entitled, ``List of Approved Spent Fuel Storage Casks: Holtec 
International HI-STORM UMAX Canister Storage System, Certificate of 
Compliance No. 1040,'' will not have a significant effect on the human 
environment. Therefore, the NRC has determined that an environmental 
impact statement is not necessary for this final rule.

VIII. Paperwork Reduction Act Statement

    This rule does not contain any information collection requirements 
and, therefore, is not subject to the requirements of the Paperwork 
Reduction Act of 1995 (44 U.S.C. 3501 et seq.).

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 current valid OMB 
control number.

IX. 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 spent nuclear fuel under a 
general license in cask designs approved by the NRC. Any nuclear power 
reactor licensee can use NRC-approved cask designs to store spent 
nuclear fuel 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 are met. A list of NRC-approved cask 
designs is contained in 10 CFR 72.214.
    By letter dated June 29, 2012, and as supplemented on July 16 and 
November 20, 2012; January 30, April 2, April 19, June 21, August 28, 
December 6, and December 31, 2013; and January 13, and January 28, 
2014, Holtec International submitted an application to add the HI-STORM 
UMAX Canister Storage System.
    The alternative to this action is to withhold approval of this new 
design and issue a site-specific license to each utility that proposes 
to use the casks. This alternative would cost both the NRC and 
utilities more time and money for each site-specific license. 
Conducting site-specific reviews would ignore the procedures and 
criteria currently in place for the addition of new cask designs that 
can be used under a general license, and would be in conflict with NWPA 
direction to the Commission to approve technologies for the use of 
spent fuel storage at the sites of civilian nuclear power reactors 
without, to the maximum extent practicable, the need for additional 
site reviews. This alternative also would tend to exclude new vendors 
from the business market without cause and would arbitrarily limit the 
choice of cask designs available to power reactor licensees. This final 
rule will eliminate the above problems and is consistent with previous 
Commission actions. Further, the rule will have no adverse effect on 
public health and safety.
    Approval of this final rule is consistent with previous NRC 
actions. Further, as documented in the SER and the environmental 
assessment, the final rule will have no adverse effect on public health 
and safety or the environment. This 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 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 therefore, 
this action is recommended.

X. 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 final 
rule affects only nuclear power plant licensees and Holtec 
International. 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).

XI. Backfitting and Issue Finality

    The NRC has determined that the backfit rule (10 CFR 72.62) does 
not apply to this final rule. Therefore, a backfit analysis is not 
required. This final rule adds CoC No. 1040 for the Holtec 
International HI-STORM UMAX Canister Storage System to the ``List of 
approved spent fuel storage casks.''
    The addition of CoC No. 1040 for the Holtec International HI-STORM 
UMAX Canister Storage System was initiated by Holtec International and 
was not submitted in response to new NRC requirements, or in response 
to an NRC request. The addition of CoC No. 1040 does not constitute 
backfitting under 10 CFR 72.62, 10 CFR 50.109(a)(1), or otherwise 
represent an inconsistency with the issue finality provisions 
applicable to combined licenses in 10 CFR part 52. Accordingly, no 
backfit analysis or additional documentation addressing the issue 
finality criteria in 10 CFR part 52 has been prepared by the staff.

XII. Congressional Review Act

    In accordance with the Congressional Review Act of 1996 (5 U.S.C. 
801-808), the NRC has determined that this action is not a rule as 
defined in the Congressional Review Act.

XIII. Availability of Documents

    The documents identified in the following table are available to 
interested persons through one or more of the following methods, as 
indicated.

------------------------------------------------------------------------
                      Document                       ADAMS Accession No.
------------------------------------------------------------------------
CoC No. 1040.......................................          ML14122A443
Safety Evaluation Report...........................          ML14122A441
Technical Specifications, Appendix A...............          ML14122A444
Technical Specifications, Appendix B...............          ML14122A442

[[Page 12078]]

 
Application........................................          ML121880102
Application supplemental July 16, 2012.............          ML12205A134
Application supplemental November 20, 2012.........          ML12348A483
Application supplemental January 30, 2013..........          ML13032A008
Application supplemental April 2, 2013.............          ML13107B249
Application supplemental April 19, 2013............          ML13114A191
Application supplemental June 21, 2013.............          ML13175A363
Application supplemental August 28, 2013...........          ML13261A062
Application supplemental December 6, 2013..........          ML13343A169
Application supplemental December 31, 2013.........          ML14002A402
Application supplemental January 13, 2014..........          ML14015A145
Application supplemental January 28, 2014..........          ML14030A055
HI-STORM FW System FSAR............................          ML12363A284
HI-STORM UMAX Canister Storage System FSAR.........          ML12363A282
------------------------------------------------------------------------

    The NRC may post materials related to this document, including 
public comments, on the Federal rulemaking Web site at http://www.regulations.gov under Docket ID NRC-2014-0120. The Federal 
rulemaking Web site allows you to receive alerts when changes or 
additions occur in a docket folder. To subscribe: (1) Navigate to the 
docket folder (NRC-2014-0120); (2) click the ``Sign up for Email 
Alerts'' link; and (3) enter your email address and select how 
frequently you would like to receive emails (daily, weekly, or 
monthly).

List of Subjects in 10 CFR Part 72

    Administrative practice and procedure, Criminal penalties, Manpower 
training programs, Nuclear materials, Occupational safety and health, 
Penalties, Radiation protection, Reporting and recordkeeping 
requirements, Security measures, Spent fuel, Whistleblowing.

    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; 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:  Atomic Energy Act secs. 51, 53, 57, 62, 63, 65, 69, 
81, 161, 182, 183, 184, 186, 187, 189, 223, 234, 274 (42 U.S.C. 
2071, 2073, 2077, 2092, 2093, 2095, 2099, 2111, 2201, 2232, 2233, 
2234, 2236, 2237, 2239, 2273, 2282, 2021); Energy Reorganization Act 
secs. 201, 202, 206, 211 (42 U.S.C. 5841, 5842, 5846, 5851); 
National Environmental Policy Act sec. 102 (42 U.S.C. 4332); Nuclear 
Waste Policy Act secs. 131, 132, 133, 135, 137, 141, 148 (42 U.S.C. 
10151, 10152, 10153, 10155, 10157, 10161, 10168); Government 
Paperwork Elimination Act sec. 1704, (44 U.S.C. 3504 note); Energy 
Policy Act of 2005, Pub. L. 109-58, 119 Stat. 788 (2005).

    Section 72.44(g) also issued under Nuclear Waste Policy Act 
secs. 142(b) and 148(c), (d) (42 U.S.C. 10162(b), 10168(c), (d)).
    Section 72.46 also issued under Atomic Energy Act sec. 189 (42 
U.S.C. 2239); Nuclear Waste Policy Act sec. 134 (42 U.S.C. 10154).
    Section 72.96(d) also issued under Nuclear Waste Policy Act sec. 
145(g) (42 U.S.C. 10165(g)).
    Subpart J also issued under Nuclear Waste Policy Act secs. 
117(a), 141(h) (42 U.S.C. 10137(a), 10161(h)).
    Subpart K also issued under Nuclear Waste Policy Act sec. 218(a) 
(42 U.S.C. 10198).


0
2. Section 72.214 is amended by adding Certificate of Compliance 1040 
to read as follows:


Sec.  72.214  List of approved spent fuel storage casks.

* * * * *
    Certificate Number: 1040.
    Initial Certificate Effective Date: April 6, 2015.
    SAR Submitted by: Holtec International, Inc.
    SAR Title: Final Safety Analysis Report for the Holtec 
International HI-STORM UMAX Canister Storage System.
    Docket Number: 72-1040.
    Certificate Expiration Date: March 6, 2035.
    Model Number: MPC-37, MPC-89.

    Dated at Rockville, Maryland, this 24th day of February 2015.

    For the Nuclear Regulatory Commission.
Mark A. Satorius,
Executive Director for Operations.
[FR Doc. 2015-05238 Filed 3-5-15; 8:45 am]
 BILLING CODE 7590-01-P



                                                                                                                                                                                              12073

                                             Rules and Regulations                                                                                         Federal Register
                                                                                                                                                           Vol. 80, No. 44

                                                                                                                                                           Friday, March 6, 2015



                                             This section of the FEDERAL REGISTER                       • NRC’s Agencywide Documents                       the Commission.’’ Section 133 of the
                                             contains regulatory documents having general            Access and Management System                          NWPA states, in part, that ‘‘[the
                                             applicability and legal effect, most of which           (ADAMS): You may obtain publicly-                     Commission] shall, by rule, establish
                                             are keyed to and codified in the Code of                available documents online in the                     procedures for the licensing of any
                                             Federal Regulations, which is published under           ADAMS Public Documents collection at                  technology approved by the
                                             50 titles pursuant to 44 U.S.C. 1510.
                                                                                                     http://www.nrc.gov/reading-rm/                        Commission under Section 219(a) [sic:
                                             The Code of Federal Regulations is sold by              adams.html. To begin the search, select               218(a)] for use at the site of any civilian
                                             the Superintendent of Documents. Prices of              ‘‘ADAMS Public Documents’’ and then                   nuclear power reactor.’’
                                             new books are listed in the first FEDERAL               select ‘‘Begin Web-based ADAMS                           To implement this mandate, the
                                             REGISTER issue of each week.                            Search.’’ For problems with ADAMS,                    Commission approved dry storage of
                                                                                                     please contact the NRC’s Public                       spent nuclear fuel in NRC-approved
                                                                                                     Document Room (PDR) reference staff at                casks under a general license by
                                             NUCLEAR REGULATORY                                      1–800–397–4209, 301–415–4737, or by                   publishing a final rule in part 72 of Title
                                             COMMISSION                                              email to pdr.resource@nrc.gov. For the                10 of the Code of Federal Regulations
                                                                                                     convenience of the reader, instructions               (10 CFR), which added a new subpart K
                                             10 CFR Part 72                                          about obtaining materials referenced in               within 10 CFR part 72 entitled, ‘‘General
                                             [NRC–2014–0120]                                         this document are provided in the                     License for Storage of Spent Fuel at
                                                                                                     ‘‘Availability of Documents’’ section.                Power Reactor Sites’’ (55 FR 29181; July
                                             RIN 3150–AJ42                                              • NRC’s PDR: You may examine and                   18, 1990). This rule also established a
                                                                                                     purchase copies of public documents at                new subpart L within 10 CFR part 72
                                             List of Approved Spent Fuel Storage                     the NRC’s PDR, Room O–1F21, One
                                             Casks: Holtec International HI–STORM                                                                          entitled, ‘‘Approval of Spent Fuel
                                                                                                     White Flint North, 11555 Rockville                    Storage Casks,’’ which contains
                                             Underground Maximum Capacity                            Pike, Rockville, Maryland 20852.
                                             Canister Storage System, Certificate of                                                                       procedures and criteria for obtaining
                                                                                                     FOR FURTHER INFORMATION CONTACT:                      NRC approval of spent fuel storage cask
                                             Compliance No. 1040
                                                                                                     Gregory R. Trussell, Office of Nuclear                designs.
                                             AGENCY:  Nuclear Regulatory                             Material Safety and Safeguards, U.S.                     The NRC published a direct final rule
                                             Commission.                                             Nuclear Regulatory Commission,                        on this amendment in the Federal
                                             ACTION: Final rule.                                     Washington, DC 20555–0001, telephone:                 Register on September 9, 2014 (79 FR
                                                                                                     301–415–6445, email: Gregory.Trussell@                53281). The NRC also concurrently
                                             SUMMARY:   The U.S. Nuclear Regulatory                  nrc.gov.                                              published an identical proposed rule on
                                             Commission (NRC) is amending its                        SUPPLEMENTARY INFORMATION:                            September 9, 2014 (79 FR 53352). The
                                             spent fuel storage regulations by adding                                                                      NRC received at least one comment that
                                             the Holtec International HI–STORM                       Table of Contents
                                                                                                                                                           is treated as a significant adverse
                                             Underground Maximum Capacity                            I. Background                                         comment on the proposed rule;
                                             (UMAX) Canister Storage System,                         II. Discussion of Changes
                                                                                                                                                           therefore, the NRC withdrew the direct
                                             Certificate of Compliance (CoC) No.                     III. Public Comment Analysis
                                                                                                     IV. Voluntary Consensus Standards                     final rule on November 19, 2014 (79 FR
                                             1040, to the ‘‘List of approved spent fuel                                                                    68763), and is proceeding, in this
                                                                                                     V. Agreement State Compatibility
                                             storage casks.’’ Holtec International’s                                                                       document, to address the comments on
                                                                                                     VI. Plain Writing
                                             intent with this design is to provide an                VII. Environmental Assessment and Finding             the proposed rule (see Section III, Public
                                             underground storage option compatible                         of No Significant Environmental Impact          Comment Analysis, of this document).
                                             with the Holtec International HI–                       VIII. Paperwork Reduction Act Statement
                                             STORM FLOOD/WIND (FW) System                            IX. Regulatory Analysis                               II. Discussion of Changes
                                             (CoC No. 1032).                                         X. Regulatory Flexibility Certification
                                                                                                     XI. Backfitting and Issue Finality
                                                                                                                                                              By letter dated June 29, 2012, and as
                                             DATES: This final rule is effective on                                                                        supplemented on July 16 and November
                                                                                                     XII. Congressional Review Act
                                             April 6, 2015.                                          XIII. Availability of Documents                       20, 2012; January 30, April 2, April 19,
                                             ADDRESSES: Please refer to Docket ID                                                                          June 21, August 28, December 6, and
                                             NRC–2014–0120 when contacting the                       I. Background                                         December 31, 2013; and January 13, and
                                             NRC about the availability of                              Section 218(a) of the Nuclear Waste                January 28, 2014, Holtec International
                                             information for this action. You may                    Policy Act (NWPA) of 1982, as                         submitted an application to add the HI–
                                             obtain publicly-available information                   amended, requires that ‘‘the Secretary                STORM UMAX Canister Storage System
                                             related to this action by any of the                    [of the Department of Energy] shall                   to the list of approved spent fuel storage
                                             following methods:                                      establish a demonstration program, in                 casks in 10 CFR part 72. The HI–
                                               • Federal Rulemaking Web site: Go to                  cooperation with the private sector, for              STORM UMAX Canister Storage System
                                             http://www.regulations.gov and search                   the dry storage of spent nuclear fuel at              is a spent fuel storage system designed
                                             for Docket ID NRC–2014–0120. Address                    civilian nuclear power reactor sites,                 to be in full compliance with the
                                             questions about NRC dockets to Carol                    with the objective of establishing one or             requirements of 10 CFR part 72. Holtec
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                                             Gallagher; telephone: 301–415–3463;                     more technologies that the [Nuclear                   International’s intent with this design is
                                             email: Carol.Gallagher@nrc.gov. For                     Regulatory] Commission may, by rule,                  to provide an underground storage
                                             technical questions, contact the                        approve for use at the sites of civilian              option compatible with the Holtec
                                             individual listed in the FOR FURTHER                    nuclear power reactors without, to the                International HI–STORM FW System as
                                             INFORMATION CONTACT section of this                     maximum extent practicable, the need                  described in the Final Safety Analysis
                                             document.                                               for additional site-specific approvals by             Report (FSAR) for the HI–STORM FW


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                                             12074                Federal Register / Vol. 80, No. 44 / Friday, March 6, 2015 / Rules and Regulations

                                             System. The underground structure                       proposed rule as a result of the public               Canister Storage System, CoC No. 1040,
                                             system is described in the FSAR for the                 comments the NRC has received.                        to the ‘‘List of approved spent fuel
                                             HI–STORM UMAX Canister Storage                                                                                storage casks’’ in 10 CFR 72.214. This
                                                                                                     Summary of Comments
                                             System. The HI–STORM UMAX                                                                                     rulemaking is not making any changes
                                             Canister Storage System stores a                           The NRC received almost a dozen                    to the regulations governing the
                                             hermetically sealed canister containing                 comments on the proposed rule, many                   standards for approval of a CoC.
                                             spent nuclear fuel (SNF) in an in-ground                raising multiple and overlapping issues.                 The CoC for the HI–STORM UMAX is
                                             vertical ventilated module (VVM). The                   Because the NRC received at least one                 being issued for 20 years in accordance
                                             HI–STORM UMAX Canister Storage                          comment that it is treating as a                      with 10 CFR part 72. According to the
                                             System is designed to provide long-term                 significant adverse comment on the                    NRC staff’s SER published in the
                                             underground storage of loaded multi-                    proposed rule (raising issues the NRC                 Federal Register under Docket ID NRC–
                                             purpose canisters (MPC) previously                      deemed serious enough to warrant a                    2014–0120, the staff has determined that
                                             certified for storage in CoC No. 1032.                  substantive response to clarify the                   the use of the HI–STORM UMAX
                                             The HI–STORM UMAX VVM is the                            record), the NRC withdrew the direct                  Canister Storage System will be
                                             underground equivalent of the HI–                       final rule and is responding to the                   conducted in compliance with the
                                             STORM FW storage module. Although                       comments here. Other comments were                    applicable regulations of 10 CFR part
                                             the storage cavity dimensions and the                   not treated as significant adverse                    72, and the CoC should be approved for
                                             air ventilation system in the HI–STORM                  comments because, in most instances,                  the initial 20-year term. There are
                                             UMAX VVM have been selected to                          they were beyond the scope of this                    currently no technical or regulatory
                                             enable it to also store all MPCs certified              rulemaking. Nonetheless, in addition to               requirements for the inclusion of AMPs
                                             for storage in the HI–STORM 100                         responding to the issues raised in the                for the initial 20-year CoC term. AMPs
                                             storage module, CoC No. 1040 does not                   comments treated as significant adverse               are required for spent fuel storage cask
                                             approve the storage of all MPCs certified               comments, the NRC is also taking this                 renewal which allows storage beyond 20
                                             for storage in the HI–STORM 100                         opportunity to respond to some of the                 years, as provided in 10 CFR 72.240.
                                             storage module in the HI–STORM                          issues raised in the comments that are                The current regulatory requirements
                                             UMAX VVM at this time. The HI–                          beyond this scope of this rulemaking in               provide the necessary defense in depth
                                             STORM UMAX Canister Storage System                      order to clarify information about the                for safe storage of spent nuclear fuel for
                                             can store either Pressurized Water                      CoC rulemaking process related to the                 at least 20 years.
                                             Reactor or Boiling Water Reactor fuel                   comments received.                                       Based on the regulations in 10 CFR
                                             assemblies in the MPC–37 or MPC–89                                                                            part 72, an AMP will be required to be
                                                                                                     Aging Management Programs                             included in any renewal application for
                                             models, respectively. The number
                                                                                                        Many of the comments the NRC                       the HI–STORM UMAX Canister Storage
                                             associated with the MPC is the
                                                                                                     received questioned the fact that aging               System, for a duration beyond the initial
                                             maximum number of fuel assemblies the
                                                                                                     management programs (AMPs) were not                   20-year term. The renewal application,
                                             MPC can contain in the fuel basket. The
                                                                                                     being established for this CoC system.                if filed, will be required to comply with
                                             external diameters of the MPC–37 and
                                                                                                     Commenters noted that the NRC has not                 the applicable regulations, and consider
                                             MPC–89 are identical to allow the use
                                                                                                     yet issued the revision to NUREG–1927                 applicable NRC aging management
                                             of a single storage module design,
                                                                                                     (‘‘Standard Review Plan for Renewal of                guidance available at the time of
                                             however the height of the MPC, as well
                                                                                                     Spent Fuel Dry Cask Storage System                    submittal. While NUREG–1927 may
                                             as the storage module and transfer cask,
                                                                                                     Licenses and Certificates of                          prove useful to applicants seeking to
                                             are variable based on the SNF to be
                                                                                                     Compliance’’), which is currently being               renew a CoC, because it does not
                                             loaded.
                                                                                                     updated to include information                        provide guidance regarding applications
                                                As documented in the safety                          regarding AMPs, among other things.                   seeking initial approval of certificates,
                                             evaluation report (SER), the NRC staff                  The comments stated that the approval                 there is no reason to await the guidance
                                             performed a detailed safety evaluation                  of this CoC system, ‘‘should be put on                before proceeding with the addition of
                                             of the proposed CoC request submitted                   hold until after the revised NUREG–                   this system to the 10 CFR part 72
                                             by Holtec International.                                1927 is final and any appropriate aging               regulations.
                                                The HI–STORM UMAX Canister                           management issues are addressed in this
                                             Storage System, when used under the                     CoC.’’                                                Inspection Access
                                             conditions specified in the CoC, the                       The comments questioned some                          Several comments also questioned the
                                             Technical Specifications (TSs), and the                 specific example AMPs discussed at                    ability of the underground storage
                                             NRC’s regulations, will meet the                        public meetings, including questions                  system to be adequately inspected and
                                             requirements of 10 CFR part 72;                         regarding an example AMP for Chloride-                potentially repaired if necessary during
                                             therefore, adequate protection of public                Induced Stress Corrosion Cracking Tests               the initial certification period of 20
                                             health and safety will continue to be                   (seismic concerns and sampling size), as              years, especially if the system was being
                                             ensured. When this final rule becomes                   well as the absence of an AMP given                   used in a coastal environment where
                                             effective, persons who hold a general                   issues with damaged fuels and the                     stress corrosion cracking could be an
                                             license under 10 CFR 72.210 may load                    ‘‘unknowns of extended storage with                   issue.
                                             spent nuclear fuel into HI–STORM                        high burnup fuel.’’ In sum, these
                                             UMAX Canister Storage Systems that                                                                            Response
                                                                                                     commenters felt that approval of CoCs,
                                             meet the criteria of CoC No. 1040 under                 such as this one, should await the                       The NRC is treating this comment as
                                             10 CFR 72.212.                                          formulation and approval of aging                     a significant adverse comment
                                                                                                                                                           warranting clarification of the record.
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                                             III. Public Comment Analysis                            management programs.
                                                                                                                                                           The NRC has evaluated the design of the
                                                The NRC received multiple comments                   Response                                              HI–STORM UMAX Canister Storage
                                             from private citizens on the companion                    These comments are outside the scope                System and has determined that the
                                             proposed rule to the direct final rule                  of this rulemaking which is limited to                design is robust, and contains numbers
                                             published on September 9, 2014. The                     amending the spent fuel storage                       of layers of acceptable confinement
                                             NRC has not made any changes to the                     regulations by adding the UMAX                        systems in compliance with 10 CFR part


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                                                                  Federal Register / Vol. 80, No. 44 / Friday, March 6, 2015 / Rules and Regulations                                         12075

                                             72 requirements. In addition, the staff is              Bankruptcy                                            High Burnup Fuel
                                             not aware of empirical evidence that
                                             supports a finding that surveillance                      A comment also raised questions                       Several comments also raised
                                             would be required in the initial                        about the implications of the potential               questions regarding the long-term
                                             certification period of the proposed                    bankruptcy of corporations that seek                  acceptability of the extended storage of
                                             CoC. This evaluation is documented in                   CoC approvals.                                        high burnup fuel (HBF).
                                             the NRC staff’s SER under Docket ID                     Response                                              Response
                                             NRC–2014–0120.
                                               Furthermore, the NRC has evaluated                       This comment is outside the scope of                  Most of the comments raising HBF as
                                             the susceptibility to and effects of stress             this rulemaking. This rulemaking would                an issue did so in the context of the
                                             corrosion cracking and other corrosion                  add a certified system to the list of spent           need for AMPs for approval of the CoC
                                             mechanisms on safety significant                        fuel systems in 10 CFR 72.214 and does                for the first 20 years, and that is beyond
                                             systems for SNF dry cask storage (DCS)                  not seek to alter the standards for                   the scope of this rulemaking, as
                                             systems during an initial certification                 approval of a CoC system. In any event,               explained above.
                                             period. The staff has determined that                   NRC regulations in 10 CFR part 72                        To the extent commenters raised
                                             the HI–STORM UMAX Canister Storage                      address the financial viability of                    issues about the storage of HBF in the
                                             System, when used within the                            licensees to ensure spent fuel                        CoC for the first 20 years, the NRC is
                                             requirements of the proposed CoC, will                  management and decommissioning are                    treating this portion of the comment as
                                             safely store SNF and prevent radiation                  funded. Pursuant to NRC requirements,                 a significant adverse comment
                                             releases and exposure consistent with                   once a general licensee accepts delivery              warranting clarification of the record.
                                             regulatory requirements.                                of a storage system authorized by a CoC,              The NRC has evaluated the acceptability
                                             Seismic Protection                                      the financial responsibility for                      of storage of HBF for the initial 20-year
                                                                                                     maintaining and decommissioning the                   certification term for the HI–STORM
                                               Several comments also raised                          system become the responsibility of the               UMAX Canister Storage System. As
                                             concerns regarding the ability of this                  general licensee (see 10 CFR 72.30(b),                documented in the NRC staff’s SER
                                             CoC system to withstand seismic events,                 (c), (d), (e), and (f)).                              under Docket ID NRC–2014–0120, the
                                             particularly if the system were to be                                                                         staff has determined that the use of the
                                             used at specific sites with known                       Flood Protection
                                                                                                                                                           HI–STORM UMAX Canister Storage
                                             seismic activity, such as San Onofre                       One comment stated that the design                 System, including storage of HBF, will
                                             Nuclear Generating Station (SONGS).                     basis of the Watts Bar 2 reactor (not yet             be conducted in compliance with the
                                             Response                                                licensed for operation) intends that safe             applicable regulations of 10 CFR part
                                                                                                     shut down could occur if there were a                 72, and the CoC should be approved for
                                                The NRC is treating this comment as                                                                        the initial 20-year term.
                                                                                                     flood event that delivered 131⁄2 feet of
                                             a significant adverse comment
                                                                                                     water at the reactor buildings. This                     Storage beyond the initial term of 20
                                             warranting clarification of the record.
                                                                                                     comment raised the concern that the                   years will require the applicant to
                                             This rulemaking would add a CoC
                                                                                                     cask waste storage in an adjacent area                submit a license renewal application
                                             system to the list of approved spent fuel
                                                                                                     would have equal or greater flooding.                 with the inclusion of AMPs addressing
                                             storage casks in 10 CFR 72.214. The
                                                                                                                                                           HBF. In that regard, a demonstration
                                             certification provided by this approval                 Response
                                                                                                                                                           project is being planned by the U.S.
                                             does not, in and of itself, authorize use
                                                                                                        This rulemaking is limited to the                  Department of Energy to provide
                                             of this system at any specific site.
                                                                                                     approval of a CoC system to be added                  confirmatory data on the performance of
                                             Instead, general licensees (a power
                                                                                                     to the list of spent fuel storage casks in            HBF in DCS. The NRC plans to evaluate
                                             reactor that stores spent fuel under a
                                                                                                     10 CFR 72.214. This rulemaking does                   the data obtained from the project to
                                             general Part 72 license) that wish to use
                                                                                                     not propose any change to the standards               confirm the accuracy of current models
                                             this system must first ensure that other
                                                                                                     for approval of a CoC, or the                         that are relied upon for authorizing the
                                             applicable requirements are met. (See 10
                                                                                                     requirements that govern the use of this              storage of HBF for extended storage
                                             CFR 72.212).
                                                                                                     CoC by a general licensee. Therefore,                 periods beyond the initial 20-year
                                                The seismic design levels of the HI–                                                                       certification term.
                                             STORM UMAX Canister Storage System                      this comment is outside the scope of
                                             as provided in this CoC are acceptable                  this rulemaking.                                      Duration of Certificate
                                             for most areas in the continental U.S.                     The NRC’s regulations at 10 CFR
                                             For locations that have potential seismic               72.212, ‘‘Conditions of a general license               Some comments also raised issues
                                             activity beyond those analyzed for this                 issued under 10 CFR 72.210,’’ require                 with the limited duration of this initial
                                             system, additional evaluations and                      that a general licensee (a power reactor              CoC for a term of only 20 years and
                                             certifications may be required before the               that stores spent fuel under a general                stated that the systems should have to
                                             system may be used in those locations.                  part 72 license) perform written                      demonstrate safe storage of nuclear fuel
                                             The NRC is currently evaluating an                      evaluations to ensure that the DCS                    for a much longer storage period.
                                             amendment request to the HI–STORM                       systems used at the location meet the                 Response
                                             UMAX Canister Storage System that                       technical requirements of the CoC. The
                                             provides additional analysis intended to                NRC inspects these evaluations prior to                 The issues of long-term storage and
                                             ensure the system’s integrity during an                 the first use of the DCS system and                   disposal of SNF are outside the scope of
                                             earthquake with higher seismic                          every three years after first use to ensure           this CoC rulemaking. This rule is
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                                             demands, including the seismic                          compliance with the terms of the CoC.                 limited to the addition of this storage
                                             demands at the location of SONGS. If                    If the CoC does not allow for water                   system to the list of approved designs in
                                             the NRC approves that amendment                         intrusion, then the general licensee is               10 CFR 72.214. The regulations
                                             request, the amended system could be                    required to provide engineered                        governing the length of the CoC term are
                                             selected for use at SONGS, provided                     measures to ensure that this condition                not within the changes proposed by this
                                             regulatory requirements are met.                        does not occur.                                       rule.


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                                             12076                Federal Register / Vol. 80, No. 44 / Friday, March 6, 2015 / Rules and Regulations

                                             Inspector General’s Report                              VI. Plain Writing                                        Holtec International HI–STORM
                                               One comment highlighted issues                                                                              UMAX Canister Storage Systems are
                                                                                                        The Plain Writing Act of 2010 (Pub.                designed to mitigate the effects of design
                                             addressed in the 2014 NRC Inspector                     L. 111–274), requires Federal agencies
                                             General’s report of the SONGS steam                                                                           basis accidents that could occur during
                                                                                                     to write documents in a clear, concise,               storage. Design basis accidents account
                                             generator replacement, entitled, ‘‘NRC                  and well-organized manner. The NRC
                                             Oversight of Licensee’s Use of 10 CFR                                                                         for human-induced events and the most
                                                                                                     has written this document to be                       severe natural phenomena reported for
                                             50.59 Process to Replace SONG’S Steam                   consistent with the Plain Writing Act as
                                             Generators (Case No. 13–006).’’                                                                               the site and surrounding area.
                                                                                                     well as the Presidential Memorandum                   Postulated accidents analyzed for an
                                             Response                                                ‘‘Plain Language in Government                        ISFSI, the type of facility at which a
                                                                                                     Writing,’’ published June 10, 1998 (63                holder of a power reactor operating
                                                The issues raised by the NRC’s IG
                                                                                                     FR 31883).                                            license would store spent fuel in casks
                                             report of the SONGS steam generator
                                             replacement are outside the scope of                    VII. Environmental Assessment and                     in accordance with 10 CFR part 72,
                                             this rulemaking. This report is                         Finding of No Significant                             include tornado winds and tornado-
                                             applicable only to that proposed steam                  Environmental Impact                                  generated missiles, a design basis
                                             generator replacement effort, and does                                                                        earthquake, a design basis flood, an
                                                                                                     A. The Action                                         accidental cask drop, lightning effects,
                                             not apply to nor is it related to this
                                             specific CoC rulemaking. Approval of                       The action is to amend 10 CFR 72.214               fire, explosions, and other incidents.
                                             this CoC is based upon a safety and                     to add the Holtec International HI–                      Considering the specific design
                                             environmental review of this specific                   STORM UMAX Canister Storage System                    requirements for each accident
                                             CoC design as submitted by the vendor.                  to the listing within the ‘‘List of                   condition, the design of the HI–STORM
                                             If power reactor licensees wish to use                  approved spent fuel storage casks’’ as                UMAX Canister Storage System would
                                             this system at their specific sites, they               CoC No. 1040. Under the National                      prevent loss of containment, shielding,
                                             must first ensure other applicable                      Environmental Policy Act of 1969, as                  and criticality control. If there is no loss
                                             regulatory requirements are met (see 10                 amended, and the NRC’s regulations in                 of containment, shielding, or criticality
                                             CFR 72.212).                                            subpart A of 10 CFR part 51,                          control, the environmental impacts
                                                                                                     ‘‘Environmental Protection Regulations                would be insignificant. In addition, any
                                             IV. Voluntary Consensus Standards                                                                             resulting occupational exposure or
                                                                                                     for Domestic Licensing and Related
                                               The National Technology Transfer                                                                            offsite dose rates from the use of the HI–
                                                                                                     Regulatory Functions,’’ the NRC has
                                             and Advancement Act of 1995 (Pub. L.                                                                          STORM UMAX Canister Storage System
                                                                                                     determined that this rule, if adopted,
                                             104–113) requires that Federal agencies                                                                       would remain well within the 10 CFR
                                                                                                     would not be a major Federal action
                                             use technical standards that are                                                                              part 20 limits. Therefore, the proposed
                                                                                                     significantly affecting the quality of the
                                             developed or adopted by voluntary                                                                             addition of CoC No. 1040 will not result
                                                                                                     human environment and, therefore, an
                                             consensus standards bodies unless the                                                                         in radiological or non-radiological
                                                                                                     environmental impact statement is not
                                             use of such a standard is inconsistent                                                                        environmental impacts that significantly
                                                                                                     required. The NRC has made a finding
                                             with applicable law or otherwise                                                                              differ from the environmental impacts
                                                                                                     of no significant impact on the basis of
                                             impractical. In this final rule, the NRC                                                                      evaluated in the environmental
                                                                                                     this environmental assessment.
                                             will add the Holtec International HI–                                                                         assessment supporting the July 18, 1990,
                                             STORM UMAX Canister Storage System                      B. The Need for the Action                            final rule. There will be no significant
                                             design to the listing in 10 CFR 72.214.                                                                       change in the types or significant
                                             This action does not constitute the                        This final rule adds CoC No. 1040 for              revisions in the amounts of effluent
                                             establishment of a standard that                        the Holtec International HI–STORM                     released, no significant increase in the
                                             contains generally applicable                           UMAX Canister Storage System design                   individual or cumulative radiation
                                             requirements.                                           within the list of approved spent fuel                exposure, and no significant increase in
                                                                                                     storage casks that power reactor                      the potential for or consequences from
                                             V. Agreement State Compatibility                        licensees can use to store spent fuel at              radiological accidents. The staff
                                                Under the ‘‘Policy Statement on                      reactor sites under a general license.                documented its safety findings for this
                                             Adequacy and Compatibility of                           Specifically, Holtec International’s                  review in the SER.
                                             Agreement State Programs’’ approved by                  intent with this design is to provide an
                                             the Commission on June 30, 1997, and                    underground storage option compatible                 D. Alternative to the Action
                                             published in the Federal Register on                    with the Holtec International HI–                       The alternative to this action is to
                                             September 3, 1997 (62 FR 46517), this                   STORM FW System.                                      withhold approval of this new design
                                             final rule is classified as Compatibility               C. Environmental Impacts of the Action                and issue a site-specific license to each
                                             Category ‘‘NRC.’’ Compatibility is not                                                                        utility that proposes to use the casks.
                                             required for Category ‘‘NRC’’                             On July 18, 1990 (55 FR 29181), the                 This alternative would cost both the
                                             regulations. The NRC program elements                   NRC issued an amendment to 10 CFR                     NRC and utilities more time and money
                                             in this category are those that relate                  part 72 to provide for the storage of                 for each site-specific license.
                                             directly to areas of regulation reserved                spent fuel under a general license in                 Conducting site-specific reviews would
                                             to the NRC by the Atomic Energy Act of                  cask designs approved by the NRC. The                 ignore the procedures and criteria
                                             1954, as amended, or the provisions of                  potential environmental impact of using               currently in place for the addition of
                                             10 CFR. Although an Agreement State                     NRC-approved storage casks was                        new cask designs that can be used under
                                             may not adopt program elements                          initially analyzed in the environmental               a general license, and would be in
                                             reserved to the NRC, it may wish to                     assessment for the 1990 final rule. The               conflict with NWPA direction to the
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                                             inform its licensees of certain                         environmental assessment for this CoC                 Commission to approve technologies for
                                             requirements via a mechanism that is                    addition tiers off of the environmental               the use of spent fuel storage at the sites
                                             consistent with the particular State’s                  assessment for the July 18, 1990, final               of civilian nuclear power reactors
                                             administrative procedure laws, but does                 rule. Tiering on past environmental                   without, to the maximum extent
                                             not confer regulatory authority on the                  assessments is a standard process under               practicable, the need for additional site
                                             State.                                                  the National Environmental Policy Act.                reviews. This alternative also would


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                                                                          Federal Register / Vol. 80, No. 44 / Friday, March 6, 2015 / Rules and Regulations                                                                                      12077

                                             tend to exclude new vendors from the                                      part 72 to provide for the storage of                                      NRC’s responsibilities for public health
                                             business market without cause and                                         spent nuclear fuel under a general                                         and safety and the common defense and
                                             would arbitrarily limit the choice of                                     license in cask designs approved by the                                    security. No other available alternative
                                             cask designs available to power reactor                                   NRC. Any nuclear power reactor                                             is believed to be as satisfactory, and
                                             licensees. This final rule will eliminate                                 licensee can use NRC-approved cask                                         therefore, this action is recommended.
                                             the above problems and is consistent                                      designs to store spent nuclear fuel if it
                                             with previous Commission actions.                                         notifies the NRC in advance, the spent                                     X. Regulatory Flexibility Certification
                                             Further, the rule will have no adverse                                    fuel is stored under the conditions                                           Under the Regulatory Flexibility Act
                                             effect on public health and safety.                                       specified in the cask’s CoC, and the                                       of 1980 (5 U.S.C. 605(b)), the NRC
                                             Therefore, the environmental impacts                                      conditions of the general license are                                      certifies that this rule will not, if issued,
                                             would be the same or less than the                                        met. A list of NRC-approved cask                                           have a significant economic impact on
                                             action.                                                                   designs is contained in 10 CFR 72.214.                                     a substantial number of small entities.
                                                                                                                          By letter dated June 29, 2012, and as
                                             E. Alternative Use of Resources                                                                                                                      This final rule affects only nuclear
                                                                                                                       supplemented on July 16 and November
                                               Approval of the addition of CoC No.                                                                                                                power plant licensees and Holtec
                                                                                                                       20, 2012; January 30, April 2, April 19,
                                             1040 would result in no irreversible                                                                                                                 International. These entities do not fall
                                                                                                                       June 21, August 28, December 6, and
                                             commitments of resources.                                                                                                                            within the scope of the definition of
                                                                                                                       December 31, 2013; and January 13, and
                                                                                                                                                                                                  small entities set forth in the Regulatory
                                             F. Agencies and Persons Contacted                                         January 28, 2014, Holtec International
                                                                                                                                                                                                  Flexibility Act or the size standards
                                                                                                                       submitted an application to add the HI-
                                               No agencies or persons outside the                                                                                                                 established by the NRC (10 CFR 2.810).
                                                                                                                       STORM UMAX Canister Storage
                                             NRC were contacted in connection with                                     System.                                                                    XI. Backfitting and Issue Finality
                                             the preparation of this environmental                                        The alternative to this action is to
                                             assessment.                                                               withhold approval of this new design                                          The NRC has determined that the
                                             G. Finding of No Significant Impact                                       and issue a site-specific license to each                                  backfit rule (10 CFR 72.62) does not
                                                                                                                       utility that proposes to use the casks.                                    apply to this final rule. Therefore, a
                                                The environmental impacts of the                                       This alternative would cost both the                                       backfit analysis is not required. This
                                             action have been reviewed under the                                       NRC and utilities more time and money                                      final rule adds CoC No. 1040 for the
                                             requirements in 10 CFR part 51. Based                                     for each site-specific license.                                            Holtec International HI–STORM UMAX
                                             on the foregoing environmental                                            Conducting site-specific reviews would                                     Canister Storage System to the ‘‘List of
                                             assessment, the NRC concludes that this                                   ignore the procedures and criteria                                         approved spent fuel storage casks.’’
                                             final rule entitled, ‘‘List of Approved                                   currently in place for the addition of
                                             Spent Fuel Storage Casks: Holtec                                                                                                                        The addition of CoC No. 1040 for the
                                                                                                                       new cask designs that can be used under                                    Holtec International HI–STORM UMAX
                                             International HI–STORM UMAX                                               a general license, and would be in
                                             Canister Storage System, Certificate of                                                                                                              Canister Storage System was initiated by
                                                                                                                       conflict with NWPA direction to the                                        Holtec International and was not
                                             Compliance No. 1040,’’ will not have a                                    Commission to approve technologies for
                                             significant effect on the human                                                                                                                      submitted in response to new NRC
                                                                                                                       the use of spent fuel storage at the sites                                 requirements, or in response to an NRC
                                             environment. Therefore, the NRC has                                       of civilian nuclear power reactors
                                             determined that an environmental                                                                                                                     request. The addition of CoC No. 1040
                                                                                                                       without, to the maximum extent                                             does not constitute backfitting under 10
                                             impact statement is not necessary for                                     practicable, the need for additional site
                                             this final rule.                                                                                                                                     CFR 72.62, 10 CFR 50.109(a)(1), or
                                                                                                                       reviews. This alternative also would                                       otherwise represent an inconsistency
                                             VIII. Paperwork Reduction Act                                             tend to exclude new vendors from the                                       with the issue finality provisions
                                             Statement                                                                 business market without cause and                                          applicable to combined licenses in 10
                                                This rule does not contain any                                         would arbitrarily limit the choice of                                      CFR part 52. Accordingly, no backfit
                                             information collection requirements                                       cask designs available to power reactor                                    analysis or additional documentation
                                             and, therefore, is not subject to the                                     licensees. This final rule will eliminate                                  addressing the issue finality criteria in
                                             requirements of the Paperwork                                             the above problems and is consistent                                       10 CFR part 52 has been prepared by the
                                             Reduction Act of 1995 (44 U.S.C. 3501                                     with previous Commission actions.                                          staff.
                                             et seq.).                                                                 Further, the rule will have no adverse
                                                                                                                       effect on public health and safety.                                        XII. Congressional Review Act
                                             Public Protection Notification                                               Approval of this final rule is
                                                                                                                       consistent with previous NRC actions.                                         In accordance with the Congressional
                                               The NRC may not conduct or sponsor,
                                                                                                                       Further, as documented in the SER and                                      Review Act of 1996 (5 U.S.C. 801–808),
                                             and a person is not required to respond
                                                                                                                       the environmental assessment, the final                                    the NRC has determined that this action
                                             to, a request for information or an
                                                                                                                       rule will have no adverse effect on                                        is not a rule as defined in the
                                             information collection requirement
                                                                                                                       public health and safety or the                                            Congressional Review Act.
                                             unless the requesting document
                                             displays a current valid OMB control                                      environment. This final rule has no                                        XIII. Availability of Documents
                                             number.                                                                   significant identifiable impact or benefit
                                                                                                                       on other Government agencies. Based on                                       The documents identified in the
                                             IX. Regulatory Analysis                                                   this regulatory analysis, the NRC                                          following table are available to
                                               On July 18, 1990 (55 FR 29181), the                                     concludes that the requirements of the                                     interested persons through one or more
                                             NRC issued an amendment to 10 CFR                                         final rule are commensurate with the                                       of the following methods, as indicated.
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                                                                                                                                                                                                                                         ADAMS Accession
                                                                                                                                 Document                                                                                                     No.

                                             CoC No. 1040 ............................................................................................................................................................................       ML14122A443
                                             Safety Evaluation Report ...........................................................................................................................................................            ML14122A441
                                             Technical Specifications, Appendix A .......................................................................................................................................                    ML14122A444
                                             Technical Specifications, Appendix B .......................................................................................................................................                    ML14122A442



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                                             12078                         Federal Register / Vol. 80, No. 44 / Friday, March 6, 2015 / Rules and Regulations

                                                                                                                                                                                                                                             ADAMS Accession
                                                                                                                                   Document                                                                                                       No.

                                             Application .................................................................................................................................................................................       ML121880102
                                             Application supplemental July 16, 2012 ....................................................................................................................................                         ML12205A134
                                             Application supplemental November 20, 2012 ..........................................................................................................................                               ML12348A483
                                             Application supplemental January 30, 2013 .............................................................................................................................                             ML13032A008
                                             Application supplemental April 2, 2013 .....................................................................................................................................                        ML13107B249
                                             Application supplemental April 19, 2013 ...................................................................................................................................                         ML13114A191
                                             Application supplemental June 21, 2013 ..................................................................................................................................                           ML13175A363
                                             Application supplemental August 28, 2013 ...............................................................................................................................                            ML13261A062
                                             Application supplemental December 6, 2013 ............................................................................................................................                              ML13343A169
                                             Application supplemental December 31, 2013 ..........................................................................................................................                               ML14002A402
                                             Application supplemental January 13, 2014 .............................................................................................................................                             ML14015A145
                                             Application supplemental January 28, 2014 .............................................................................................................................                             ML14030A055
                                             HI–STORM FW System FSAR ..................................................................................................................................................                          ML12363A284
                                             HI–STORM UMAX Canister Storage System FSAR ................................................................................................................                                         ML12363A282



                                                The NRC may post materials related                                       148 (42 U.S.C. 10151, 10152, 10153, 10155,                                  DEPARTMENT OF ENERGY
                                             to this document, including public                                          10157, 10161, 10168); Government
                                             comments, on the Federal rulemaking                                         Paperwork Elimination Act sec. 1704, (44                                    10 CFR Part 431
                                             Web site at http://www.regulations.gov                                      U.S.C. 3504 note); Energy Policy Act of 2005,
                                                                                                                                                                                                     [Docket Number EERE–2008–BT–STD–
                                             under Docket ID NRC–2014–0120. The                                          Pub. L. 109–58, 119 Stat. 788 (2005).
                                                                                                                                                                                                     0015]
                                             Federal rulemaking Web site allows you                                        Section 72.44(g) also issued under Nuclear
                                             to receive alerts when changes or                                                                                                                       RIN 1904–AB86
                                                                                                                         Waste Policy Act secs. 142(b) and 148(c), (d)
                                             additions occur in a docket folder. To                                      (42 U.S.C. 10162(b), 10168(c), (d)).
                                             subscribe: (1) Navigate to the docket                                                                                                                   Energy Conservation Program: Energy
                                                                                                                           Section 72.46 also issued under Atomic                                    Conservation Standards for Walk-In
                                             folder (NRC–2014–0120); (2) click the                                       Energy Act sec. 189 (42 U.S.C. 2239); Nuclear
                                             ‘‘Sign up for Email Alerts’’ link; and (3)                                                                                                              Coolers and Freezers; Correction
                                                                                                                         Waste Policy Act sec. 134 (42 U.S.C. 10154).
                                             enter your email address and select how                                       Section 72.96(d) also issued under Nuclear                                AGENCY:  Office of Energy Efficiency and
                                             frequently you would like to receive                                        Waste Policy Act sec. 145(g) (42 U.S.C.                                     Renewable Energy, Department of
                                             emails (daily, weekly, or monthly).                                         10165(g)).                                                                  Energy.
                                             List of Subjects in 10 CFR Part 72                                            Subpart J also issued under Nuclear Waste                                 ACTION: Final rule; correction.
                                                                                                                         Policy Act secs. 117(a), 141(h) (42 U.S.C.
                                               Administrative practice and                                               10137(a), 10161(h)).                                                        SUMMARY:    On June 3, 2014, the U.S.
                                             procedure, Criminal penalties,                                                Subpart K also issued under Nuclear Waste                                 Department of Energy (DOE) issued a
                                             Manpower training programs, Nuclear                                         Policy Act sec. 218(a) (42 U.S.C. 10198).                                   final rule adopting conservation
                                             materials, Occupational safety and                                                                                                                      standards for some classes of walk-in
                                             health, Penalties, Radiation protection,                                    ■ 2. Section 72.214 is amended by                                           cooler and walk-in freezer components.
                                             Reporting and recordkeeping                                                 adding Certificate of Compliance 1040                                       The final rule was published with
                                             requirements, Security measures, Spent                                      to read as follows:                                                         typographical errors to some of the
                                             fuel, Whistleblowing.                                                                                                                                   reported values. DOE is providing
                                               For the reasons set out in the                                            § 72.214 List of approved spent fuel
                                                                                                                         storage casks.
                                                                                                                                                                                                     corrections to address these errors.
                                             preamble and under the authority of the                                                                                                                 Neither the errors nor the corrections in
                                             Atomic Energy Act of 1954, as amended;                                      *      *     *     *     *                                                  this document affect the substance of
                                             the Energy Reorganization Act of 1974,                                         Certificate Number: 1040.                                                the rulemaking or any of the
                                             as amended; and 5 U.S.C. 552 and 553,                                                                                                                   conclusions reached in support of the
                                                                                                                            Initial Certificate Effective Date: April
                                             the NRC is adopting the following                                                                                                                       final rule.
                                                                                                                         6, 2015.
                                             amendments to 10 CFR part 72.                                                                                                                           DATES: This correction is effective
                                                                                                                            SAR Submitted by: Holtec
                                             PART 72—LICENSING                                                                                                                                       March 6, 2015.
                                                                                                                         International, Inc.
                                             REQUIREMENTS FOR THE                                                                                                                                    FOR FURTHER INFORMATION CONTACT:
                                                                                                                            SAR Title: Final Safety Analysis                                         Mr. John Cymbalsky, U.S. Department of
                                             INDEPENDENT STORAGE OF SPENT
                                                                                                                         Report for the Holtec International HI–                                     Energy, Office of Energy Efficiency and
                                             NUCLEAR FUEL, HIGH-LEVEL
                                                                                                                         STORM UMAX Canister Storage                                                 Renewable Energy, Building
                                             RADIOACTIVE WASTE AND
                                             REACTOR-RELATED GREATER THAN                                                System.                                                                     Technologies Program, EE–5B, 1000
                                             CLASS C WASTE                                                                  Docket Number: 72–1040.                                                  Independence Avenue SW.,
                                                                                                                                                                                                     Washington, DC 20585–0121.
                                                                                                                            Certificate Expiration Date: March 6,
                                             ■ 1. The authority citation for part 72                                                                                                                 Telephone: (202) 287–1692. Email:
                                                                                                                         2035.
                                             continues to read as follows:                                                                                                                           walk-in_coolers_and_walk-in_freezers@
                                               Authority: Atomic Energy Act secs. 51, 53,
                                                                                                                            Model Number: MPC–37, MPC–89.                                            EE.Doe.Gov.
                                             57, 62, 63, 65, 69, 81, 161, 182, 183, 184, 186,                              Dated at Rockville, Maryland, this 24th day                                  Mr. Michael Kido, U.S. Department of
                                             187, 189, 223, 234, 274 (42 U.S.C. 2071, 2073,                                                                                                          Energy, Office of the General Counsel,
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                                                                                                                         of February 2015.
                                             2077, 2092, 2093, 2095, 2099, 2111, 2201,                                                                                                               GC–33, 1000 Independence Avenue
                                                                                                                           For the Nuclear Regulatory Commission.
                                             2232, 2233, 2234, 2236, 2237, 2239, 2273,                                                                                                               SW., Washington, DC 20585–0121.
                                             2282, 2021); Energy Reorganization Act secs.                                Mark A. Satorius,
                                                                                                                                                                                                     Telephone: (202) 586–8145. Email:
                                             201, 202, 206, 211 (42 U.S.C. 5841, 5842,                                   Executive Director for Operations.
                                             5846, 5851); National Environmental Policy
                                                                                                                                                                                                     Michael.Kido@hq.doe.gov.
                                                                                                                         [FR Doc. 2015–05238 Filed 3–5–15; 8:45 am]
                                             Act sec. 102 (42 U.S.C. 4332); Nuclear Waste                                                                                                            SUPPLEMENTARY INFORMATION: The
                                             Policy Act secs. 131, 132, 133, 135, 137, 141,                              BILLING CODE 7590–01–P                                                      Department of Energy (‘‘DOE’’) is


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Document Created: 2018-02-21 09:33:22
Document Modified: 2018-02-21 09:33:22
CategoryRegulatory Information
CollectionFederal Register
sudoc ClassAE 2.7:
GS 4.107:
AE 2.106:
PublisherOffice of the Federal Register, National Archives and Records Administration
SectionRules and Regulations
ActionFinal rule.
DatesThis final rule is effective on April 6, 2015.
ContactGregory R. Trussell, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, telephone: 301-415-6445, email: [email protected]
FR Citation80 FR 12073 
RIN Number3150-AJ42
CFR AssociatedAdministrative Practice and Procedure; Criminal Penalties; Manpower Training Programs; Nuclear Materials; Occupational Safety and Health; Penalties; Radiation Protection; Reporting and Recordkeeping Requirements; Security Measures; Spent Fuel and Whistleblowing

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