List of Approved Spent Fuel Storage Casks: NUHOMS®-24PT4 Revision, 9501-9504 [05-3738]
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9501
Rules and Regulations
Federal Register
Vol. 70, No. 38
Monday, February 28, 2005
This section of the FEDERAL REGISTER
contains regulatory documents having general
applicability and legal effect, most of which
are keyed to and codified in the Code of
Federal Regulations, which is published under
50 titles pursuant to 44 U.S.C. 1510.
The Code of Federal Regulations is sold by
the Superintendent of Documents. Prices of
new books are listed in the first FEDERAL
REGISTER issue of each week.
NUCLEAR REGULATORY
COMMISSION
10 CFR Part 72
RIN 3150–AH63
List of Approved Spent Fuel Storage
Casks: NUHOMS–24PT4 Revision
Nuclear Regulatory
Commission.
ACTION: Direct final rule.
AGENCY:
SUMMARY: The Nuclear Regulatory
Commission (NRC) is amending its
regulations revising the Transnuclear,
Inc., Standardized Advanced
NUHOMS System listing within the
‘‘List of approved spent fuel storage
casks’’ to include Amendment No. 1 to
Certificate of Compliance Number (CoC
No.) 1029. Amendment No. 1 will add
another Dry Shielded Canister (DSC),
designated NUHOMS–24PT4, to the
authorized contents of the Standardized
Advanced NUHOMS System. Also, the
rule will be amended to correct a
typographical error that incorrectly
states the expiration date of the CoC.
DATES: The final rule is effective May
16, 2005, unless significant adverse
comments are received by March 30,
2005. A significant adverse comment is
a comment where the commenter
explains why the rule would be
inappropriate, including challenges to
the rule’s underlying premise or
approach, or would be ineffective or
unacceptable without a change. If the
rule is withdrawn, timely notice will be
published in the Federal Register.
ADDRESSES: You may submit comments
by any one of the following methods.
Please include the following number
(RIN 3150–AH63) in the subject line of
your comments. Comments on
rulemakings submitted in writing or in
electronic form will be made available
for public inspection. Because your
comments will not be edited to remove
any identifying or contact information,
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16:26 Feb 25, 2005
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the NRC cautions you against including
personal information such as social
security numbers and birth dates in
your submission.
Mail comments to: Secretary, U.S.
Nuclear Regulatory Commission,
Washington, DC 20555–0001, ATTN:
Rulemakings and Adjudications Staff.
E-mail comments to: SECY@nrc.gov. If
you do not receive a reply e-mail
confirming that we have received your
comments, contact us directly at (301)
415–1966. You may also submit
comments via the NRC’s rulemaking
website at https://ruleforum.llnl.gov.
Address questions about our rulemaking
website to Carol Gallagher (301) 415–
5905; e-mail cag@nrc.gov. Comments
can also be submitted via the Federal
eRulemaking Portal https://
www.regulations.gov.
Hand deliver comments to: 11555
Rockville Pike, Rockville, Maryland
20852, between 7:30 a.m. and 4:15 p.m.
Federal workdays (telephone (301) 415–
1966).
Fax comments to: Secretary, U.S.
Nuclear Regulatory Commission at (301)
415–1101.
Publicly available documents related
to this rulemaking may be viewed
electronically on the public computers
located at the NRC’s Public Document
Room (PDR), O–1F21, One White Flint
North, 11555 Rockville Pike, Rockville,
Maryland. Selected documents,
including comments, can be viewed and
downloaded electronically via the NRC
rulemaking website at https://
ruleforum.llnl.gov.
Publicly available documents created
or received at the NRC after November
1, 1999, are available electronically at
the NRC’s Electronic Reading Room at
https://www.nrc.gov/NRC/ADAMS/
index.html. From this site, the public
can gain entry into the NRC’s
Agencywide Document Access and
Management System (ADAMS), which
provides text and image files of NRC’s
public documents. If you do not have
access to ADAMS or if there are
problems in accessing the documents
located in ADAMS, contact the NRC
PDR Reference staff at 1–800–397–4209,
301–415–4737, or by e-mail to
pdr@nrc.gov. An electronic copy of the
proposed CoC and preliminary safety
evaluation report (SER) can be found
under ADAMS Accession No.
ML043650049.
CoC No. 1029, the revised Technical
Specifications (TS), the underlying SER
PO 00000
Frm 00001
Fmt 4700
Sfmt 4700
for Amendment No. 1, and the
Environmental Assessment (EA), are
available for inspection at the NRC PDR,
11555 Rockville Pike, Rockville, MD.
Single copies of these documents may
be obtained from Jayne M. McCausland,
Office of Nuclear Material Safety and
Safeguards, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001, telephone (301) 415–6219, e-mail
jmm2@nrc.gov.
FOR FURTHER INFORMATION CONTACT:
Jayne M. McCausland, telephone (301)
415–6219, e-mail jmm2@nrc.gov, of the
Office of Nuclear Material Safety and
Safeguards, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001.
SUPPLEMENTARY INFORMATION:
Background
Section 218(a) of the Nuclear Waste
Policy Act of 1982, as amended
(NWPA), requires that ‘‘[t]he Secretary
[of the Department of Energy (DOE)]
shall establish a demonstration program,
in cooperation with the private sector,
for the dry storage of spent nuclear fuel
at civilian nuclear power reactor sites,
with the objective of establishing one or
more technologies that the [Nuclear
Regulatory] Commission may, by rule,
approve for use at the sites of civilian
nuclear power reactors without, to the
maximum extent practicable, the need
for additional site-specific approvals by
the Commission.’’ Section 133 of the
NWPA states, in part, that ‘‘[t]he
Commission shall, by rule, establish
procedures for the licensing of any
technology approved by the
Commission under Section 218(a) for
use at the site of any civilian nuclear
power reactor.’’
To implement this mandate, the NRC
approved dry storage of spent nuclear
fuel in NRC-approved casks under a
general license by publishing a final
rule in 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’’ containing procedures
and criteria for obtaining NRC approval
of spent fuel storage cask designs. The
NRC subsequently issued a final rule on
January 6, 2003 (68 FR 463), that
approved the Transnuclear, Inc. (TN),
Standardized Advanced NUHOMS
System cask design and added it to the
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Procedural Background
list of NRC-approved cask designs in
§ 72.214 as CoC No. 1029.
Discussion
On April 30, 2003, and as
supplemented on March 12, July 2, and
September 14, 2004, the certificate
holder, TN, submitted an application to
the NRC to amend CoC No. 1029 to add
another DSC, designated NUHOMS–
24PT4, to the authorized contents of the
Standardized Advanced NUHOMS
System. This canister is designed to
accommodate 24 intact Pressurized
Water Reactor fuel assemblies with or
without integral burnable poison rods or
integral fuel burnable absorber rods, or
up to 12 damaged fuel assemblies in
lieu of an equal number of intact
assemblies. It is designed for use with
the existing Advanced NUHOMS
Horizontal Storage Module and transfer
in the NUHOMS OS197H transfer cask,
with a maximum heat load of 24
kilowatts (kW), under a general license.
The specific changes requested in
Amendment No. 1 to CoC No. 1029 are
listed in the SER. No other changes to
the Standardized Advanced NUHOMS
System design were requested in this
application. In addition, the NRC staff
has determined that there is still
reasonable assurance that public health
and safety and the environment will be
adequately protected.
This direct final rule revises the
Standardized Advanced NUHOMS
System cask design listing in § 72.214
by adding Amendment No. 1 to CoC No.
1029. The amendment consists of
changes to the TS as described above.
The particular TS which are changed
are identified in the NRC staff’s SER for
Amendment No. 1. Also, the NRC staff
is revising the rule text to correct a
typographical error that incorrectly
states the expiration date of the CoC.
The correct expiration date, as listed in
CoC No. 1029 for the Standardized
Advanced NUHOMS System, is
February 5, 2023.
The amended Standardized Advanced
NUHOMS System, when used in
accordance with the conditions
specified in the CoC, the TS, and NRC
regulations, will meet the requirements
of Part 72; thus, adequate protection of
public health and safety will continue to
be ensured.
Discussion of Amendments by Section
Section 72.214 List of Approved Spent
Fuel Storage Casks
Certificate No. 1029 is revised by
adding the effective date of Amendment
Number 1 and changing the expiration
date of the CoC to February 5, 2023.
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This rule is limited to the changes
contained in Amendment 1 to CoC No.
1029 and does not include other aspects
of the Standardized Advanced
NUHOMS System cask design. The
NRC is using the ‘‘direct final rule
procedure’’ to issue this amendment
because it represents a limited and
routine change to an existing CoC that
is expected to be noncontroversial.
Adequate protection of public health
and safety continues to be ensured. The
amendment to the rule will become
effective on May 16, 2005. However, if
the NRC receives significant adverse
comments by March 30, 2005, then the
NRC will publish a document that
withdraws this action and will address
the comments received in response to
the proposed amendments published
elsewhere in this issue of the Federal
Register, in a subsequent final rule.
A significant adverse comment is a
comment where the commenter
explains why the rule would be
inappropriate, including challenges to
the rule’s underlying premise or
approach, or would be ineffective or
unacceptable without a change. A
comment is adverse and significant if:
(1) The comment opposes the rule and
provides a reason sufficient to require a
substantive response in a notice-andcomment process. For example, in a
substantive response:
(a) The comment causes the NRC staff
to reevaluate (or reconsider) its position
or conduct additional analysis;
(b) The comment raises an issue
serious enough to warrant a substantive
response to clarify or complete the
record; or
(c) The comment raises a relevant
issue that was not previously addressed
or considered by the NRC staff.
(2) The comment proposes a change
or an addition to the rule, and it is
apparent that the rule would be
ineffective or unacceptable without
incorporation of the change or addition.
(3) The comment causes the NRC staff
to make a change (other than editorial)
to the CoC or TS.
Voluntary Consensus Standards
The National Technology Transfer Act
of 1995 (Pub. L. 104–113) requires that
Federal agencies use technical standards
that are developed or adopted by
voluntary consensus standards bodies
unless the use of such a standard is
inconsistent with applicable law or
otherwise impractical. In this direct
final rule, the NRC is revising the
Standardized Advanced NUHOMS
System design listed in § 72.214 (List of
NRC-approved spent fuel storage cask
PO 00000
Frm 00002
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designs). This action does not constitute
the establishment of a standard that
establishes generally applicable
requirements.
Agreement State Compatibility
Under the ‘‘Policy Statement on
Adequacy and Compatibility of
Agreement State Programs’’ approved by
the Commission on June 30, 1997, and
published in the Federal Register on
September 3, 1997 (62 FR 46517), this
rule is classified as Compatibility
Category ‘‘NRC.’’ Compatibility is not
required for Category ‘‘NRC’’
regulations. The NRC program elements
in this category are those that relate
directly to areas of regulation reserved
to the NRC by the Atomic Energy Act of
1954, as amended (AEA), or the
provisions of Title 10 of the Code of
Federal Regulations. Although an
Agreement State may not adopt program
elements reserved to NRC, it may wish
to inform its licensees of certain
requirements via a mechanism that is
consistent with the particular State’s
administrative procedure laws but does
not confer regulatory authority on the
State.
Plain Language
The Presidential Memorandum dated
June 1, 1998, entitled ‘‘Plain Language
in Government Writing,’’ directed that
the Government’s writing be in plain
language. The NRC requests comments
on this direct final rule specifically with
respect to the clarity and effectiveness
of the language used. Comments should
be sent to the address listed under the
heading ADDRESSES above.
Finding of No Significant
Environmental Impact: Availability
Under the National Environmental
Policy Act of 1969, as amended, and the
NRC regulations in Subpart A of 10 CFR
Part 51, the NRC has determined that
this rule, if adopted, would not be a
major Federal action significantly
affecting the quality of the human
environment and, therefore, an
environmental impact statement is not
required. The rule would amend the
CoC for the Standardized Advanced
NUHOMS System within the list of
approved spent fuel storage casks that
power reactor licensees can use to store
spent fuel at reactor sites under a
general license. The amendment will
modify the present cask system design
to add another DSC, designated
NUHOMS–24PT4, to the authorized
contents of the Standardized Advanced
NUHOMS System. This canister is
designed to accommodate 24 intact
Pressurized Water Reactor fuel
assemblies with or without integral
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burnable poison rods or integral fuel
burnable absorber rods, or up to 12
damaged fuel assemblies in lieu of an
equal number of intact assemblies. It is
designed for use with the existing
Advanced NUHOMS Horizontal
Storage Module and transfer in the
NUHOMS OS197H transfer cask, with
a maximum heat load of 24 kW. Also,
the expiration date of the CoC will be
changed to correct a typographical error.
Specifically, the expiration date will be
changed to February 5, 2023, as listed in
CoC No. 1029 for the Standardized
Advanced NUHOMS System.
The environmental assessment and
finding of no significant impact on
which this determination is based are
available for inspection at the NRC
Public Document Room, 11555
Rockville Pike, Rockville, MD. Single
copies of the environmental assessment
and finding of no significant impact are
available from Jayne M. McCausland,
Office of Nuclear Material Safety and
Safeguards, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001, telephone (301) 415–6219, e-mail
jmm2@nrc.gov.
Paperwork Reduction Act Statement
This direct final rule does not contain
a new or amended information
collection requirement subject to the
Paperwork Reduction Act of 1995 (44
U.S.C. 3501 et seq.). Existing
requirements were approved by the
Office of Management and Budget
(OMB), Approval Number 3150–0132.
Public Protection Notification
The NRC may not conduct or sponsor,
and a person is not required to respond
to, a request for information or an
information collection requirement
unless the requesting document
displays a currently valid OMB control
number.
Regulatory Analysis
On July 18, 1990 (55 FR 29181), the
NRC issued an amendment to 10 CFR
Part 72 to provide for the storage of
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, 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 § 72.214. On January 6, 2003 (68 FR
463), the NRC issued an amendment to
Part 72 that approved the Standardized
Advanced NUHOMS System by adding
it to the list of NRC-approved cask
designs in § 72.214. On April 30, 2003,
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as supplemented on March 12, July 2,
and September 14, 2004, the certificate
holder, TN, submitted an application to
the NRC to amend CoC No. 1029 to
modify the present cask system design
to add another DSC, designated
NUHOMS–24PT4, to the authorized
contents of the Standardized Advanced
NUHOMS System. This canister is
designed to accommodate 24 intact
Pressurized Water Reactor fuel
assemblies with or without integral
burnable poison rods or integral fuel
burnable absorber rods, or up to 12
damaged fuel assemblies in lieu of an
equal number of intact assemblies. It is
designed for use with the existing
Advanced NUHOMS Horizontal
Storage Module and transfer in the
NUHOMS OS197H transfer cask, with
a maximum heat load of 24 kW.
The alternative to this action is to
withhold approval of this amended cask
system design and issue an exemption
to each general license. This alternative
would cost both the NRC and the
utilities more time and money because
each utility would have to pursue an
exemption.
Approval of the direct final rule will
eliminate this problem and is consistent
with previous NRC actions. Further, the
direct final rule will have no adverse
effect on public health and safety. This
direct final rule has no significant
identifiable impact or benefit on other
Government agencies. Based on this
discussion of the benefits and impacts
of the alternatives, the NRC concludes
that the requirements of the direct final
rule are commensurate with the NRC’s
responsibilities for public health and
safety and the common defense and
security. No other available alternative
is believed to be as satisfactory, and
thus, this action is recommended.
Regulatory Flexibility Certification
In accordance with the Regulatory
Flexibility Act of 1980 (5 U.S.C. 605(b)),
the NRC certifies that this rule will not,
if issued, have a significant economic
impact on a substantial number of small
entities. This direct final rule affects
only the licensing and operation of
nuclear power plants, independent
spent fuel storage facilities, and TN. The
companies that own these plants do not
fall within the scope of the definition of
‘‘small entities’’ set forth in the
Regulatory Flexibility Act or the Small
Business Size Standards set out in
regulations issued by the Small
Business Administration at 13 CFR Part
121.
Backfit Analysis
The NRC has determined that the
backfit rule (10 CFR 50.109 or 10 CFR
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9503
72.62) does not apply to this direct final
rule because this amendment does not
involve any provisions that would
impose backfits as defined. Therefore, a
backfit analysis is not required.
Small Business Regulatory Enforcement
Fairness Act
In accordance with the Small
Business Regulatory Enforcement
Fairness Act of 1996, the NRC has
determined that this action is not a
major rule and has verified this
determination with the Office of
Information and Regulatory Affairs,
Office of Management and Budget.
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.
I
PART 72—LICENSING
REQUIREMENTS FOR THE
INDEPENDENT STORAGE OF SPENT
NUCLEAR FUEL, HIGH-LEVEL
RADIOACTIVE WASTE, AND
REACTOR–RELATED GREATER THAN
CLASS C WASTE
1. The authority citation for part 72
continues to read as follows:
I
Authority: Secs. 51, 53, 57, 62, 63, 65, 69,
81, 161, 182, 183, 184, 186, 187, 189, 68 Stat.
929, 930, 932, 933, 934, 935, 948, 953, 954,
955, as amended, sec. 234, 83 Stat. 444, as
amended (42 U.S.C. 2071, 2073, 2077, 2092,
2093, 2095, 2099, 2111, 2201, 2232, 2233,
2234, 2236, 2237, 2238, 2282); sec. 274, Pub.
L. 86–373, 73 Stat. 688, as amended (42
U.S.C. 2021); sec. 201, as amended, 202, 206,
88 Stat. 1242, as amended, 1244, 1246 (42
U.S.C. 5841, 5842, 5846); Pub. L. 95–601, sec.
10, 92 Stat. 2951 as amended by Pub. L. 102–
486, sec. 7902, 106 Stat. 3123 (42 U.S.C.
5851); sec. 102, Pub. L. 91–190, 83 Stat. 853
(42 U.S.C. 4332); secs. 131, 132, 133, 135,
137, 141, Pub. L. 97–425, 96 Stat. 2229, 2230,
2232, 2241, sec. 148, Pub. L. 100–203, 101
Stat. 1330–235 (42 U.S.C. 10151, 10152,
10153, 10155, 10157, 10161, 10168); sec.
1704, 112 Stat. 2750 (44 U.S.C. 3504 note).
Section 72.44(g) also issued under secs.
142(b) and 148(c), (d), Pub. L. 100–203, 101
Stat. 1330–232, 1330–236 (42 U.S.C.
10162(b), 10168(c), (d)). Section 72.46 also
issued under sec. 189, 68 Stat. 955 (42 U.S.C.
2239); sec. 134, Pub. L. 97–425, 96 Stat. 2230
(42 U.S.C. 10154). Section 72.96(d) also
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issued under sec. 145(g), Pub. L. 100–203,
101 Stat. 1330–235 (42 U.S.C. 10165(g)).
Subpart J also issued under secs. 2(2), 2(15),
2(19), 117(a), 141(h), Pub. L. 97–425, 96 Stat.
2202, 2203, 2204, 2222, 2244 (42 U.S.C.
10101, 10137(a), 10161(h)). Subparts K and L
are also issued under sec. 133, 98 Stat. 2230
(42 U.S.C. 10153) and sec. 218(a), 96 Stat.
2252 (42 U.S.C. 10198).
2. In § 72.214, Certificate of
Compliance 1029 is revised to read as
follows:
I
§ 72.214 List of approved spent fuel
storage casks.
*
*
*
*
*
Certificate Number: 1029.
Initial Certificate Effective Date:
February 5, 2003.
Amendment Number 1 Effective Date:
May 16, 2005.
SAR Submitted by: Transnuclear, Inc.
SAR Title: Final Safety Analysis
Report for the Standardized Advanced
NUHOMS Horizontal Modular Storage
System for Irradiated Nuclear Fuel.
Docket Number: 72–1029.
Certificate Expiration Date: February
5, 2023.
Model Number: Standardized
Advanced NUHOMS–24PT1,
NUHOMS–24PT4.
Dated at Rockville, Maryland, this 14th day
of February, 2005.
For the Nuclear Regulatory Commission.
Luis A. Reyes,
Executive Director for Operations.
[FR Doc. 05–3738 Filed 2–25–05; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
10 CFR Part 72
RIN 3150–AH64
List of Approved Spent Fuel Storage
Casks: HI–STORM 100 Revision
Nuclear Regulatory
Commission.
ACTION: Direct final rule.
AGENCY:
SUMMARY: The Nuclear Regulatory
Commission (NRC) is amending its
regulations revising the Holtec
International HI–STORM 100 cask
system listing within the ‘‘List of
approved spent fuel storage casks’’ to
include Amendment No. 2 to Certificate
of Compliance Number (CoC No.) 1014.
Amendment No. 2 will modify the cask
design to include changes to materials
used in construction, changes to the
types of fuel that can be loaded, changes
to shielding and confinement
methodologies and assumptions,
revisions to various temperature limits,
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changes in allowable fuel enrichments,
and other changes to reflect current NRC
staff guidance and use of industry
codes, under a general license.
DATES: The final rule is effective May
16, 2005, unless significant adverse
comments are received by March 30,
2005. A significant adverse comment is
a comment where the commenter
explains why the rule would be
inappropriate, including challenges to
the rule’s underlying premise or
approach, or would be ineffective or
unacceptable without a change. If the
rule is withdrawn, timely notice will be
published in the Federal Register.
ADDRESSES: You may submit comments
by any one of the following methods.
Please include the following number
(RIN 3150–AH64) in the subject line of
your comments. Comments on
rulemakings submitted in writing or in
electronic form will be made available
for public inspection. Because your
comments will not be edited to remove
any identifying or contact information,
the NRC cautions you against including
personal information such as social
security numbers and birth dates in
your submission.
Mail comments to: Secretary, U.S.
Nuclear Regulatory Commission,
Washington, DC 20555–0001, ATTN:
Rulemakings and Adjudications Staff.
E-mail comments to: SECY@nrc.gov. If
you do not receive a reply e-mail
confirming that we have received your
comments, contact us directly at (301)
415–1966. You may also submit
comments via the NRC’s rulemaking
Web site at https://ruleforum.llnl.gov.
Address questions about our rulemaking
Web site to Carol Gallagher (301) 415–
5905; e-mail cag@nrc.gov. Comments
can also be submitted via the Federal
eRulemaking Portal https://
www.regulations.gov.
Hand deliver comments to: 11555
Rockville Pike, Rockville, Maryland
20852, between 7:30 a.m. and 4:15 p.m.
Federal workdays (telephone (301) 415–
1966).
Fax comments to: Secretary, U.S.
Nuclear Regulatory Commission at (301)
415–1101.
Publicly available documents related
to this rulemaking may be viewed
electronically on the public computers
located at the NRC’s Public Document
Room (PDR), O–1F21, One White Flint
North, 11555 Rockville Pike, Rockville,
Maryland. Selected documents,
including comments, can be viewed and
downloaded electronically via the NRC
rulemaking Web site at https://
ruleforum.llnl.gov.
Publicly available documents created
or received at the NRC after November
PO 00000
Frm 00004
Fmt 4700
Sfmt 4700
1, 1999, are available electronically at
the NRC’s Electronic Reading Room at
https://www.nrc.gov/NRC/ADAMS/
index.html. From this site, the public
can gain entry into the NRC’s
Agencywide Document Access and
Management System (ADAMS), which
provides text and image files of NRC’s
public documents. If you do not have
access to ADAMS or if there are
problems in accessing the documents
located in ADAMS, contact the NRC
PDR Reference staff at 1–800–397–4209,
(301) 415–4737, or by e-mail to
pdr@nrc.gov. An electronic copy of the
proposed CoC and preliminary safety
evaluation report (SER) can be found
under ADAMS Accession No.
ML043640359.
CoC No. 1014, the revised Technical
Specifications (TS), the underlying SER
for Amendment No. 2, and the
Environmental Assessment (EA), are
available for inspection at the NRC PDR,
11555 Rockville Pike, Rockville, MD.
Single copies of these documents may
be obtained from Jayne M. McCausland,
Office of Nuclear Material Safety and
Safeguards, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001, telephone (301) 415–6219, e-mail
jmm2@nrc.gov.
FOR FURTHER INFORMATION CONTACT:
Jayne M. McCausland, telephone (301)
415–6219, e-mail jmm2@nrc.gov, of the
Office of Nuclear Material Safety and
Safeguards, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001.
SUPPLEMENTARY INFORMATION:
Background
Section 218(a) of the Nuclear Waste
Policy Act of 1982, as amended
(NWPA), requires that ‘‘[t]he Secretary
[of the Department of Energy (DOE)]
shall establish a demonstration program,
in cooperation with the private sector,
for the dry storage of spent nuclear fuel
at civilian nuclear power reactor sites,
with the objective of establishing one or
more technologies that the [Nuclear
Regulatory] Commission may, by rule,
approve for use at the sites of civilian
nuclear power reactors without, to the
maximum extent practicable, the need
for additional site-specific approvals by
the Commission.’’ Section 133 of the
NWPA states, in part, that ‘‘[t]he
Commission shall, by rule, establish
procedures for the licensing of any
technology approved by the
Commission under Section 218(a) for
use at the site of any civilian nuclear
power reactor.’’
To implement this mandate, the NRC
approved dry storage of spent nuclear
fuel in NRC-approved casks under a
E:\FR\FM\28FER1.SGM
28FER1
Agencies
[Federal Register Volume 70, Number 38 (Monday, February 28, 2005)]
[Rules and Regulations]
[Pages 9501-9504]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 05-3738]
========================================================================
Rules and Regulations
Federal Register
________________________________________________________________________
This section of the FEDERAL REGISTER contains regulatory documents
having general applicability and legal effect, most of which are keyed
to and codified in the Code of Federal Regulations, which is published
under 50 titles pursuant to 44 U.S.C. 1510.
The Code of Federal Regulations is sold by the Superintendent of Documents.
Prices of new books are listed in the first FEDERAL REGISTER issue of each
week.
========================================================================
Federal Register / Vol. 70, No. 38 / Monday, February 28, 2005 /
Rules and Regulations
[[Page 9501]]
NUCLEAR REGULATORY COMMISSION
10 CFR Part 72
RIN 3150-AH63
List of Approved Spent Fuel Storage Casks: NUHOMS[supreg]-24PT4
Revision
AGENCY: Nuclear Regulatory Commission.
ACTION: Direct final rule.
-----------------------------------------------------------------------
SUMMARY: The Nuclear Regulatory Commission (NRC) is amending its
regulations revising the Transnuclear, Inc., Standardized Advanced
NUHOMS[reg] System listing within the ``List of approved spent fuel
storage casks'' to include Amendment No. 1 to Certificate of Compliance
Number (CoC No.) 1029. Amendment No. 1 will add another Dry Shielded
Canister (DSC), designated NUHOMS[supreg]-24PT4, to the authorized
contents of the Standardized Advanced NUHOMS[supreg] System. Also, the
rule will be amended to correct a typographical error that incorrectly
states the expiration date of the CoC.
DATES: The final rule is effective May 16, 2005, unless significant
adverse comments are received by March 30, 2005. A significant adverse
comment is a comment where the commenter explains why the rule would be
inappropriate, including challenges to the rule's underlying premise or
approach, or would be ineffective or unacceptable without a change. If
the rule is withdrawn, timely notice will be published in the Federal
Register.
ADDRESSES: You may submit comments by any one of the following methods.
Please include the following number (RIN 3150-AH63) in the subject line
of your comments. Comments on rulemakings submitted in writing or in
electronic form will be made available for public inspection. Because
your comments will not be edited to remove any identifying or contact
information, the NRC cautions you against including personal
information such as social security numbers and birth dates in your
submission.
Mail comments to: Secretary, U.S. Nuclear Regulatory Commission,
Washington, DC 20555-0001, ATTN: Rulemakings and Adjudications Staff.
E-mail comments to: SECY@nrc.gov. If you do not receive a reply e-
mail confirming that we have received your comments, contact us
directly at (301) 415-1966. You may also submit comments via the NRC's
rulemaking website at https://ruleforum.llnl.gov. Address questions
about our rulemaking website to Carol Gallagher (301) 415-5905; e-mail
cag@nrc.gov. Comments can also be submitted via the Federal eRulemaking
Portal https://www.regulations.gov.
Hand deliver comments to: 11555 Rockville Pike, Rockville, Maryland
20852, between 7:30 a.m. and 4:15 p.m. Federal workdays (telephone
(301) 415-1966).
Fax comments to: Secretary, U.S. Nuclear Regulatory Commission at
(301) 415-1101.
Publicly available documents related to this rulemaking may be
viewed electronically on the public computers located at the NRC's
Public Document Room (PDR), O-1F21, One White Flint North, 11555
Rockville Pike, Rockville, Maryland. Selected documents, including
comments, can be viewed and downloaded electronically via the NRC
rulemaking website at https://ruleforum.llnl.gov.
Publicly available documents created or received at the NRC after
November 1, 1999, are available electronically at the NRC's Electronic
Reading Room at https://www.nrc.gov/NRC/ADAMS/. From this
site, the public can gain entry into the NRC's Agencywide Document
Access and Management System (ADAMS), which provides text and image
files of NRC's public documents. If you do not have access to ADAMS or
if there are problems in accessing the documents located in ADAMS,
contact the NRC PDR Reference staff at 1-800-397-4209, 301-415-4737, or
by e-mail to pdr@nrc.gov. An electronic copy of the proposed CoC and
preliminary safety evaluation report (SER) can be found under ADAMS
Accession No. ML043650049.
CoC No. 1029, the revised Technical Specifications (TS), the
underlying SER for Amendment No. 1, and the Environmental Assessment
(EA), are available for inspection at the NRC PDR, 11555 Rockville
Pike, Rockville, MD. Single copies of these documents may be obtained
from Jayne M. McCausland, Office of Nuclear Material Safety and
Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001, telephone (301) 415-6219, e-mail jmm2@nrc.gov.
FOR FURTHER INFORMATION CONTACT: Jayne M. McCausland, telephone (301)
415-6219, e-mail jmm2@nrc.gov, of the Office of Nuclear Material Safety
and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001.
SUPPLEMENTARY INFORMATION:
Background
Section 218(a) of the Nuclear Waste Policy Act of 1982, as amended
(NWPA), requires that ``[t]he Secretary [of the Department of Energy
(DOE)] shall establish a demonstration program, in cooperation with the
private sector, for the dry storage of spent nuclear fuel at civilian
nuclear power reactor sites, with the objective of establishing one or
more technologies that the [Nuclear Regulatory] Commission may, by
rule, approve for use at the sites of civilian nuclear power reactors
without, to the maximum extent practicable, the need for additional
site-specific approvals by the Commission.'' Section 133 of the NWPA
states, in part, that ``[t]he Commission shall, by rule, establish
procedures for the licensing of any technology approved by the
Commission under Section 218(a) for use at the site of any civilian
nuclear power reactor.''
To implement this mandate, the NRC approved dry storage of spent
nuclear fuel in NRC-approved casks under a general license by
publishing a final rule in 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'' containing
procedures and criteria for obtaining NRC approval of spent fuel
storage cask designs. The NRC subsequently issued a final rule on
January 6, 2003 (68 FR 463), that approved the Transnuclear, Inc. (TN),
Standardized Advanced NUHOMS[supreg] System cask design and added it to
the
[[Page 9502]]
list of NRC-approved cask designs in Sec. 72.214 as CoC No. 1029.
Discussion
On April 30, 2003, and as supplemented on March 12, July 2, and
September 14, 2004, the certificate holder, TN, submitted an
application to the NRC to amend CoC No. 1029 to add another DSC,
designated NUHOMS[supreg]-24PT4, to the authorized contents of the
Standardized Advanced NUHOMS[supreg] System. This canister is designed
to accommodate 24 intact Pressurized Water Reactor fuel assemblies with
or without integral burnable poison rods or integral fuel burnable
absorber rods, or up to 12 damaged fuel assemblies in lieu of an equal
number of intact assemblies. It is designed for use with the existing
Advanced NUHOMS[supreg] Horizontal Storage Module and transfer in the
NUHOMS[supreg] OS197H transfer cask, with a maximum heat load of 24
kilowatts (kW), under a general license. The specific changes requested
in Amendment No. 1 to CoC No. 1029 are listed in the SER. No other
changes to the Standardized Advanced NUHOMS[supreg] System design were
requested in this application. In addition, the NRC staff has
determined that there is still reasonable assurance that public health
and safety and the environment will be adequately protected.
This direct final rule revises the Standardized Advanced
NUHOMS[supreg] System cask design listing in Sec. 72.214 by adding
Amendment No. 1 to CoC No. 1029. The amendment consists of changes to
the TS as described above. The particular TS which are changed are
identified in the NRC staff's SER for Amendment No. 1. Also, the NRC
staff is revising the rule text to correct a typographical error that
incorrectly states the expiration date of the CoC. The correct
expiration date, as listed in CoC No. 1029 for the Standardized
Advanced NUHOMS[supreg] System, is February 5, 2023.
The amended Standardized Advanced NUHOMS[supreg] System, when used
in accordance with the conditions specified in the CoC, the TS, and NRC
regulations, will meet the requirements of Part 72; thus, adequate
protection of public health and safety will continue to be ensured.
Discussion of Amendments by Section
Section 72.214 List of Approved Spent Fuel Storage Casks
Certificate No. 1029 is revised by adding the effective date of
Amendment Number 1 and changing the expiration date of the CoC to
February 5, 2023.
Procedural Background
This rule is limited to the changes contained in Amendment 1 to CoC
No. 1029 and does not include other aspects of the Standardized
Advanced NUHOMS[supreg] System cask design. The NRC is using the
``direct final rule procedure'' to issue this amendment because it
represents a limited and routine change to an existing CoC that is
expected to be noncontroversial. Adequate protection of public health
and safety continues to be ensured. The amendment to the rule will
become effective on May 16, 2005. However, if the NRC receives
significant adverse comments by March 30, 2005, then the NRC will
publish a document that withdraws this action and will address the
comments received in response to the proposed amendments published
elsewhere in this issue of the Federal Register, in a subsequent final
rule.
A significant adverse comment is a comment where the commenter
explains why the rule would be inappropriate, including challenges to
the rule's underlying premise or approach, or would be ineffective or
unacceptable without a change. A comment is adverse and significant if:
(1) The comment opposes the rule and provides a reason sufficient
to require a substantive response in a notice-and-comment process. For
example, in a substantive response:
(a) The comment causes the NRC staff to reevaluate (or reconsider)
its position or conduct additional analysis;
(b) The comment raises an issue serious enough to warrant a
substantive response to clarify or complete the record; or
(c) The comment raises a relevant issue that was not previously
addressed or considered by the NRC staff.
(2) The comment proposes a change or an addition to the rule, and
it is apparent that the rule would be ineffective or unacceptable
without incorporation of the change or addition.
(3) The comment causes the NRC staff to make a change (other than
editorial) to the CoC or TS.
Voluntary Consensus Standards
The National Technology Transfer Act of 1995 (Pub. L. 104-113)
requires that Federal agencies use technical standards that are
developed or adopted by voluntary consensus standards bodies unless the
use of such a standard is inconsistent with applicable law or otherwise
impractical. In this direct final rule, the NRC is revising the
Standardized Advanced NUHOMS[supreg] System design listed in Sec.
72.214 (List of NRC-approved spent fuel storage cask designs). This
action does not constitute the establishment of a standard that
establishes generally applicable requirements.
Agreement State Compatibility
Under the ``Policy Statement on Adequacy and Compatibility of
Agreement State Programs'' approved by the Commission on June 30, 1997,
and published in the Federal Register on September 3, 1997 (62 FR
46517), this rule is classified as Compatibility Category ``NRC.''
Compatibility is not required for Category ``NRC'' regulations. The NRC
program elements in this category are those that relate directly to
areas of regulation reserved to the NRC by the Atomic Energy Act of
1954, as amended (AEA), or the provisions of Title 10 of the Code of
Federal Regulations. Although an Agreement State may not adopt program
elements reserved to NRC, it may wish to inform its licensees of
certain requirements via a mechanism that is consistent with the
particular State's administrative procedure laws but does not confer
regulatory authority on the State.
Plain Language
The Presidential Memorandum dated June 1, 1998, entitled ``Plain
Language in Government Writing,'' directed that the Government's
writing be in plain language. The NRC requests comments on this direct
final rule specifically with respect to the clarity and effectiveness
of the language used. Comments should be sent to the address listed
under the heading ADDRESSES above.
Finding of No Significant Environmental Impact: Availability
Under the National Environmental Policy Act of 1969, as amended,
and the NRC regulations in Subpart A of 10 CFR Part 51, the NRC has
determined that this rule, if adopted, would not be a major Federal
action significantly affecting the quality of the human environment
and, therefore, an environmental impact statement is not required. The
rule would amend the CoC for the Standardized Advanced NUHOMS[supreg]
System within the list of approved spent fuel storage casks that power
reactor licensees can use to store spent fuel at reactor sites under a
general license. The amendment will modify the present cask system
design to add another DSC, designated NUHOMS[supreg]-24PT4, to the
authorized contents of the Standardized Advanced NUHOMS[supreg] System.
This canister is designed to accommodate 24 intact Pressurized Water
Reactor fuel assemblies with or without integral
[[Page 9503]]
burnable poison rods or integral fuel burnable absorber rods, or up to
12 damaged fuel assemblies in lieu of an equal number of intact
assemblies. It is designed for use with the existing Advanced
NUHOMS[supreg] Horizontal Storage Module and transfer in the
NUHOMS[supreg] OS197H transfer cask, with a maximum heat load of 24 kW.
Also, the expiration date of the CoC will be changed to correct a
typographical error. Specifically, the expiration date will be changed
to February 5, 2023, as listed in CoC No. 1029 for the Standardized
Advanced NUHOMS[supreg] System.
The environmental assessment and finding of no significant impact
on which this determination is based are available for inspection at
the NRC Public Document Room, 11555 Rockville Pike, Rockville, MD.
Single copies of the environmental assessment and finding of no
significant impact are available from Jayne M. McCausland, Office of
Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory
Commission, Washington, DC 20555-0001, telephone (301) 415-6219, e-mail
jmm2@nrc.gov.
Paperwork Reduction Act Statement
This direct final rule does not contain a new or amended
information collection requirement subject to the Paperwork Reduction
Act of 1995 (44 U.S.C. 3501 et seq.). Existing requirements were
approved by the Office of Management and Budget (OMB), Approval Number
3150-0132.
Public Protection Notification
The NRC may not conduct or sponsor, and a person is not required to
respond to, a request for information or an information collection
requirement unless the requesting document displays a currently valid
OMB control number.
Regulatory Analysis
On July 18, 1990 (55 FR 29181), the NRC issued an amendment to 10
CFR Part 72 to provide for the storage of 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, 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 Sec. 72.214. On January 6, 2003 (68 FR 463), the NRC
issued an amendment to Part 72 that approved the Standardized Advanced
NUHOMS[supreg] System by adding it to the list of NRC-approved cask
designs in Sec. 72.214. On April 30, 2003, as supplemented on March
12, July 2, and September 14, 2004, the certificate holder, TN,
submitted an application to the NRC to amend CoC No. 1029 to modify the
present cask system design to add another DSC, designated
NUHOMS[supreg]-24PT4, to the authorized contents of the Standardized
Advanced NUHOMS[supreg] System. This canister is designed to
accommodate 24 intact Pressurized Water Reactor fuel assemblies with or
without integral burnable poison rods or integral fuel burnable
absorber rods, or up to 12 damaged fuel assemblies in lieu of an equal
number of intact assemblies. It is designed for use with the existing
Advanced NUHOMS[supreg] Horizontal Storage Module and transfer in the
NUHOMS[supreg] OS197H transfer cask, with a maximum heat load of 24 kW.
The alternative to this action is to withhold approval of this
amended cask system design and issue an exemption to each general
license. This alternative would cost both the NRC and the utilities
more time and money because each utility would have to pursue an
exemption.
Approval of the direct final rule will eliminate this problem and
is consistent with previous NRC actions. Further, the direct final rule
will have no adverse effect on public health and safety. This direct
final rule has no significant identifiable impact or benefit on other
Government agencies. Based on this discussion of the benefits and
impacts of the alternatives, the NRC concludes that the requirements of
the direct final rule are commensurate with the NRC's responsibilities
for public health and safety and the common defense and security. No
other available alternative is believed to be as satisfactory, and
thus, this action is recommended.
Regulatory Flexibility Certification
In accordance with the Regulatory Flexibility Act of 1980 (5 U.S.C.
605(b)), the NRC certifies that this rule will not, if issued, have a
significant economic impact on a substantial number of small entities.
This direct final rule affects only the licensing and operation of
nuclear power plants, independent spent fuel storage facilities, and
TN. The companies that own these plants do not fall within the scope of
the definition of ``small entities'' set forth in the Regulatory
Flexibility Act or the Small Business Size Standards set out in
regulations issued by the Small Business Administration at 13 CFR Part
121.
Backfit Analysis
The NRC has determined that the backfit rule (10 CFR 50.109 or 10
CFR 72.62) does not apply to this direct final rule because this
amendment does not involve any provisions that would impose backfits as
defined. Therefore, a backfit analysis is not required.
Small Business Regulatory Enforcement Fairness Act
In accordance with the Small Business Regulatory Enforcement
Fairness Act of 1996, the NRC has determined that this action is not a
major rule and has verified this determination with the Office of
Information and Regulatory Affairs, Office of Management and Budget.
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.
0
For the reasons set out in the preamble and under the authority of the
Atomic Energy Act of 1954, as amended; the Energy Reorganization Act of
1974, as amended; and 5 U.S.C. 552 and 553; the NRC is adopting the
following amendments to 10 CFR part 72.
PART 72--LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF
SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-
RELATED GREATER THAN CLASS C WASTE
0
1. The authority citation for part 72 continues to read as follows:
Authority: Secs. 51, 53, 57, 62, 63, 65, 69, 81, 161, 182, 183,
184, 186, 187, 189, 68 Stat. 929, 930, 932, 933, 934, 935, 948, 953,
954, 955, as amended, sec. 234, 83 Stat. 444, as amended (42 U.S.C.
2071, 2073, 2077, 2092, 2093, 2095, 2099, 2111, 2201, 2232, 2233,
2234, 2236, 2237, 2238, 2282); sec. 274, Pub. L. 86-373, 73 Stat.
688, as amended (42 U.S.C. 2021); sec. 201, as amended, 202, 206, 88
Stat. 1242, as amended, 1244, 1246 (42 U.S.C. 5841, 5842, 5846);
Pub. L. 95-601, sec. 10, 92 Stat. 2951 as amended by Pub. L. 102-
486, sec. 7902, 106 Stat. 3123 (42 U.S.C. 5851); sec. 102, Pub. L.
91-190, 83 Stat. 853 (42 U.S.C. 4332); secs. 131, 132, 133, 135,
137, 141, Pub. L. 97-425, 96 Stat. 2229, 2230, 2232, 2241, sec. 148,
Pub. L. 100-203, 101 Stat. 1330-235 (42 U.S.C. 10151, 10152, 10153,
10155, 10157, 10161, 10168); sec. 1704, 112 Stat. 2750 (44 U.S.C.
3504 note).
Section 72.44(g) also issued under secs. 142(b) and 148(c), (d),
Pub. L. 100-203, 101 Stat. 1330-232, 1330-236 (42 U.S.C. 10162(b),
10168(c), (d)). Section 72.46 also issued under sec. 189, 68 Stat.
955 (42 U.S.C. 2239); sec. 134, Pub. L. 97-425, 96 Stat. 2230 (42
U.S.C. 10154). Section 72.96(d) also
[[Page 9504]]
issued under sec. 145(g), Pub. L. 100-203, 101 Stat. 1330-235 (42
U.S.C. 10165(g)). Subpart J also issued under secs. 2(2), 2(15),
2(19), 117(a), 141(h), Pub. L. 97-425, 96 Stat. 2202, 2203, 2204,
2222, 2244 (42 U.S.C. 10101, 10137(a), 10161(h)). Subparts K and L
are also issued under sec. 133, 98 Stat. 2230 (42 U.S.C. 10153) and
sec. 218(a), 96 Stat. 2252 (42 U.S.C. 10198).
0
2. In Sec. 72.214, Certificate of Compliance 1029 is revised to read
as follows:
Sec. 72.214 List of approved spent fuel storage casks.
* * * * *
Certificate Number: 1029.
Initial Certificate Effective Date: February 5, 2003.
Amendment Number 1 Effective Date: May 16, 2005.
SAR Submitted by: Transnuclear, Inc.
SAR Title: Final Safety Analysis Report for the Standardized
Advanced NUHOMS[supreg] Horizontal Modular Storage System for
Irradiated Nuclear Fuel.
Docket Number: 72-1029.
Certificate Expiration Date: February 5, 2023.
Model Number: Standardized Advanced NUHOMS[supreg]-24PT1,
NUHOMS[supreg]-24PT4.
Dated at Rockville, Maryland, this 14th day of February, 2005.
For the Nuclear Regulatory Commission.
Luis A. Reyes,
Executive Director for Operations.
[FR Doc. 05-3738 Filed 2-25-05; 8:45 am]
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