List of Approved Spent Fuel Storage Casks: Standardized NUHOMS® 32PT, -24PHB, and -24PTH Revision 8, 55023-55026 [05-18662]
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Rules and Regulations
Federal Register
Vol. 70, No. 181
Tuesday, September 20, 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–AH77
List of Approved Spent Fuel Storage
Casks: Standardized NUHOMS 32PT,
–24PHB, and –24PTH Revision 8
Nuclear Regulatory
Commission.
ACTION: Direct final rule.
AGENCY:
SUMMARY: The Nuclear Regulatory
Commission (NRC) is amending its
regulations revising the Transnuclear,
Inc., Standardized NUHOMS System
listing within the ‘‘List of approved
spent fuel storage casks’’ to include
Amendment No. 8 to Certificate of
Compliance Number (CoC No.) 1004.
Amendment No. 8 to the Standardized
NUHOMS System CoC will add a new
spent fuel storage and transfer system,
designated the NUHOMS–24PTH
System, and modify the NUHOMS–
32PT and –24PHB dry shielded canister
designs.
DATES: The final rule is effective
December 5, 2005, unless significant
adverse comments are received by
October 20, 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rule is withdrawn, timely notice will be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–AH77) 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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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
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, Technical Specifications
(TS), and preliminary safety evaluation
report (SER) can be found under
ADAMS Accession No. ML051610554.
CoC No. 1004, the revised TS, the
underlying SER for Amendment No. 8,
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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
December 22, 1994 (59 FR 65898), that
approved the Standardized NUHOMS
System (NUHOMS–24P and –52B)
cask designs and added them to the list
of NRC-approved cask designs in
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Federal Register / Vol. 70, No. 181 / Tuesday, September 20, 2005 / Rules and Regulations
§ 72.214 as CoC No. 1004. Amendments
3, 5, and 6, respectively, added the
–61BT, –32PT, and –24PHB designs to
the Standardized NUHOMS System.
Discussion
On September 19, 2003, and as
supplemented on January 22, April 21,
May 28, July 6, August 16, September
17, September 23, October 8, October
11, October 26, November 29, 2004, and
January 14, March 15, June 10, and July
20, 2005, the certificate holder,
Transnuclear, Inc. (TN), submitted an
application to the NRC to amend CoC
No. 1004 to add a new spent fuel storage
and transfer system, designated the
NUHOMS–24PTH System, and to
modify the NUHOMS–32PT and
–24PHB dry shielded canister (DSC)
designs. The NUHOMS–24PTH System
consists of new or modified
components: (1) The –24PTH DSC; (2) a
new –24PTH DSC basket design; (3) a
modified horizontal storage module
(HSM), designated the HSM–H; and (4)
a modified transfer cask (TC),
designated the OS 197FC TC. The
NUHOMS–24PTH System is designed
to store fuel with maximum average
burnup of up to 62 gigawatts-day/metric
ton of uranium (GWd/MTU); maximum
average initial enrichment of 5.0 weight
percent; minimum cooling time of 3.0
years; and maximum heat load of 40.8
kilowatts (kW) per DSC. TS 1.2.18 and
Table 1–1l are augmented to restrict the
–24PTH DSC basket heat loading
patterns to those analyzed in the Safety
Analysis Report (SAR), and TS 1.2.17c
is revised to delete the use of air for
blowdown of the –24PTH DSC before
drying operations. The changes to the
–32PT and –24PHB systems include: (1)
Revising the –32PT DSC Fuel
Specification and Fuel Qualification
Tables to include low enrichment and
reconstituted fuel; (2) revising the
–32PT DSC Fuel Specification Tables to
show minimum boron loading
concentration; (3) expanding the
authorized contents for the –24PHB
DSC; (4) revising the TC/DSC handling
and lifting height specifications in TS
1.2.10 and 1.2.13; and (5) clarifying DSC
surface contamination actions in TS
1.2.12. No other changes to the
Standardized NUHOMS System cask
design were requested in this
application. The NRC staff performed a
detailed safety evaluation of the
proposed CoC amendment request and
found that an acceptable safety margin
is maintained. In addition, the NRC staff
has determined that there continues to
be reasonable assurance that public
health and safety and the environment
will be adequately protected.
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This direct final rule revises the
Standardized NUHOMS System cask
design listing in § 72.214 by adding
Amendment No. 8 to CoC No. 1004. 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.
8.
The amended Standardized
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. 1004 is revised by
adding the effective date of Amendment
Number 8.
Procedural Background
On May 25, 2005, a direct final rule
(70 FR 29931) and companion proposed
rule (70 FR 30015) were published in
the Federal Register, to revise the cask
system listing for the TN Standardized
NUHOMS System, by adding
Amendment No. 8 to the list of
approved spent fuel storage casks in 10
CFR 72.214. After the rules were
published, staff became aware of needed
changes in the TS associated with the
CoC, and on July 15, 2005, the NRC
withdrew the direct final rule (70 FR
40879) and the proposed rule (70 FR
40924). This direct final rule includes
the original Amendment No. 8 changes,
the revised TS 1.2.17c and 1.2.18, Table
1–1l, and additional changes, as
discussed above. These additional
changes were originally to be addressed
as a subsequent amendment. However,
the withdrawal of the May 25, 2005,
package allowed the staff to combine
this information into Amendment No. 8.
This results in a more effective and
efficient use of resources.
This rule is limited to the changes
contained in Amendment No. 8 to CoC
No. 1004 and does not include other
aspects of the Standardized NUHOMS
System 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 December 5,
2005. However, if the NRC receives
significant adverse comments by
October 20, 2005, then the NRC will
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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. 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.
These comments will be addressed in
a subsequent final rule. The NRC will
not initiate a second comment period on
this action.
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 revises the
Standardized NUHOMS System cask
design listed in § 72.214 (List of NRCapproved 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’’
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Federal Register / Vol. 70, No. 181 / Tuesday, September 20, 2005 / Rules and Regulations
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 is not a major Federal action
significantly affecting the quality of the
human environment and, therefore, an
environmental impact statement is not
required. The rule amends the CoC for
the Standardized 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 adds a new spent fuel
storage and transfer system, designated
the NUHOMS–24PTH System, and
modifies the NUHOMS–32PT and
–24PHB DSC designs. The NUHOMS–
24PTH System consists of new or
modified components: (1) The –24PTH
DSC; (2) a new –24PTH DSC basket
design; (3) a modified horizontal storage
module, designated the HSM–H; and (4)
a modified transfer cask, designated the
OS 197FC TC. The NUHOMS–24PTH
System is designed to store fuel with
maximum average burnup of up to 62
GWd/MTU; maximum average initial
enrichment of 5.0 weight percent;
minimum cooling time of 3.0 years; and
maximum heat load of 40.8 kW per
DSC. TS 1.2.18 and Table 1–1l are
augmented to restrict the –24PTH DSC
basket heat loading patterns to those
analyzed in the SAR, and TS 1.2.17c is
revised to delete the use of air for
blowdown of the –24PTH DSC before
drying operations. The changes to the
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–32PT and –24PHB systems include: (1)
Revising the –32PT DSC Fuel
Specification and Fuel Qualification
Tables to include low enrichment and
reconstituted fuel; (2) revising the
–32PT DSC Fuel Specification Tables to
show minimum boron loading
concentration; (3) expanding the
authorized contents for the –24PHB
DSC; (4) revising the TC/DSC handling
and lifting height specifications in TS
1.2.10 and 1.2.13; and (5) clarifying DSC
surface contamination actions in TS
1.2.12. The EA 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 EA 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,
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 December 22, 1994 (59
FR 65898), the NRC issued an
amendment to part 72 that approved the
Standardized NUHOMS System
(NUHOMS–24P and –52B) by adding it
to the list of NRC-approved cask designs
in § 72.214. Amendments 3, 5, and 6,
respectively, added the –61BT, –32PT,
and –24PHB designs to the
Standardized NUHOMS System. On
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55025
September 19, 2003, and as
supplemented on January 22, April 21,
May 28, July 6, August 16, September
17, September 23, October 8, October
11, October 26, November 29, 2004, and
January 14, March 15, June 10, and July
20, 2005, the certificate holder, TN,
submitted an application to the NRC to
amend CoC No. 1004 to add a new spent
fuel storage and transfer system,
designated the NUHOMS–24PTH
System, and to modify the NUHOMS
–32PT and –24PHB DSC designs. The
NUHOMS–24PTH System consists of
new or modified components: (1) The
–24PTH DSC; (2) a new –24PTH DSC
basket design; (3) a modified horizontal
storage module, designated the HSM–H;
and (4) a modified transfer cask,
designated the OS 197FC TC. The
NUHOMS–24PTH System is designed
to store fuel with maximum average
burnup of up to 62 GWd/MTU;
maximum average initial enrichment of
5.0 weight percent; minimum cooling
time of 3.0 years; and maximum heat
load of 40.8 kW per DSC. TS 1.2.18 and
Table 1–1l are augmented to restrict the
–24PTH DSC basket heat loading
patterns to those analyzed in the SAR,
and TS 1.2.17c is revised to delete the
use of air for blowdown of the –24PTH
DSC prior to drying operations. The
changes to the –32PT and –24PHB
systems include: (1) Revising the –32PT
DSC Fuel Specification and Fuel
Qualification Tables to include low
enrichment and reconstituted fuel; (2)
revising the –32PT DSC Fuel
Specification Tables to show minimum
boron loading concentration; (3)
expanding the authorized contents for
the –24PHB DSC; (4) revising the TC/
DSC handling and lifting height
specifications in TS 1.2.10 and 1.2.13;
and (5) clarifying DSC surface
contamination actions in TS 1.2.12.
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
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Federal Register / Vol. 70, No. 181 / Tuesday, September 20, 2005 / Rules and Regulations
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.
Congressional Review Act
In accordance with the Congressional
Review Act of 1996, the NRC has
determined that this action is not a
major rule and has verified this
determination with the Office of
Information and Regulatory 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
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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
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, 2224 (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 1004 is revised to read as
follows:
I
§ 72.214 List of approved spent fuel
storage casks.
*
*
*
*
*
Certificate Number: 1004.
Initial Certificate Effective Date:
January 23, 1995.
Amendment Number 1 Effective Date:
April 27, 2000.
Amendment Number 2 Effective Date:
September 5, 2000.
Amendment Number 3 Effective Date:
September 12, 2001.
Amendment Number 4 Effective Date:
February 12, 2002.
Amendment Number 5 Effective Date:
January 7, 2004.
Amendment Number 6 Effective Date:
December 22, 2003.
Amendment Number 7 Effective Date:
March 2, 2004.
Amendment Number 8 Effective Date:
December 5, 2005.
SAR Title: Final Safety Analysis
Report for the Standardized NUHOMS
Horizontal Modular Storage System for
Irradiated Nuclear Fuel.
Docket Number: 72–1004.
Certificate Expiration Date: January
23, 2015.
Model Number: NUHOMS–24P,
–52B, –61BT, –32PT, –24PHB, and
–24PTH.
*
*
*
*
*
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Dated at Rockville, Maryland, this 1st day
of September 2005.
For the Nuclear Regulatory Commission.
Luis A. Reyes,
Executive Director for Operations.
[FR Doc. 05–18662 Filed 9–19–05; 8:45 am]
BILLING CODE 7590–01–P
DEPARTMENT OF HEALTH AND
HUMAN SERVICES
Food and Drug Administration
21 CFR Part 872
[Docket No. 2005N–0338]
Medical Devices; Dental Devices;
Classification of Oral Rinse to Reduce
the Adhesion of Dental Plaque
AGENCY:
Food and Drug Administration,
HHS.
ACTION:
Final rule.
SUMMARY: The Food and Drug
Administration (FDA) is classifying the
oral rinse to reduce the adhesion of
dental plaque device into class II
(special controls). The special control
that will apply to the device is the
guidance document entitled ‘‘Class II
Special Controls Guidance Document:
Oral Rinse to Reduce the Adhesion of
Dental Plaque.’’ The agency is
classifying the device into class II
(special controls) in order to provide a
reasonable assurance of safety and
effectiveness of the device. Elsewhere in
this issue of the Federal Register, FDA
is publishing a notice of availability of
a guidance document that is the special
control for this device.
DATES: This rule is effective October 20,
2005. The reclassification was effective
March 28, 2005.
FOR FURTHER INFORMATION CONTACT:
Robert Betz, Center for Devices and
Radiological Health (HFZ–410), Food
and Drug Administration, 9200
Corporate Blvd., Rockville, MD 20850,
301–827–5283, ext. 125.
SUPPLEMENTARY INFORMATION:
I. Background
In accordance with section 513(f)(1) of
the Federal Food, Drug, and Cosmetic
Act (the act) (21 U.S.C. 360c(f)(1)),
devices that were not in commercial
distribution before May 28, 1976, the
date of enactment of the Medical Device
Amendments of 1976 (the amendments),
generally referred to as postamendments
devices, are classified automatically by
statute into class III without any FDA
rulemaking process. These devices
remain in class III and require
premarket approval, unless and until
E:\FR\FM\20SER1.SGM
20SER1
]]>Agencies
[Federal Register Volume 70, Number 181 (Tuesday, September 20, 2005)]
[Rules and Regulations]
[Pages 55023-55026]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 05-18662]
========================================================================
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. 181 / Tuesday, September 20, 2005 /
Rules and Regulations
[[Page 55023]]
NUCLEAR REGULATORY COMMISSION
10 CFR Part 72
RIN 3150-AH77
List of Approved Spent Fuel Storage Casks: Standardized
NUHOMS[supreg] 32PT, -24PHB, and -24PTH Revision 8
AGENCY: Nuclear Regulatory Commission.
ACTION: Direct final rule.
-----------------------------------------------------------------------
SUMMARY: The Nuclear Regulatory Commission (NRC) is amending its
regulations revising the Transnuclear, Inc., Standardized
NUHOMS[supreg] System listing within the ``List of approved spent fuel
storage casks'' to include Amendment No. 8 to Certificate of Compliance
Number (CoC No.) 1004. Amendment No. 8 to the Standardized
NUHOMS[supreg] System CoC will add a new spent fuel storage and
transfer system, designated the NUHOMS[supreg]-24PTH System, and modify
the NUHOMS[supreg]-32PT and -24PHB dry shielded canister designs.
DATES: The final rule is effective December 5, 2005, unless significant
adverse comments are received by October 20, 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-AH77) 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 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,
Technical Specifications (TS), and preliminary safety evaluation report
(SER) can be found under ADAMS Accession No. ML051610554.
CoC No. 1004, the revised TS, the underlying SER for Amendment No.
8, 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
December 22, 1994 (59 FR 65898), that approved the Standardized
NUHOMS[supreg] System (NUHOMS[supreg]-24P and -52B) cask designs and
added them to the list of NRC-approved cask designs in
[[Page 55024]]
Sec. 72.214 as CoC No. 1004. Amendments 3, 5, and 6, respectively,
added the -61BT, -32PT, and -24PHB designs to the Standardized
NUHOMS[supreg] System.
Discussion
On September 19, 2003, and as supplemented on January 22, April 21,
May 28, July 6, August 16, September 17, September 23, October 8,
October 11, October 26, November 29, 2004, and January 14, March 15,
June 10, and July 20, 2005, the certificate holder, Transnuclear, Inc.
(TN), submitted an application to the NRC to amend CoC No. 1004 to add
a new spent fuel storage and transfer system, designated the
NUHOMS[supreg]-24PTH System, and to modify the NUHOMS[supreg]-32PT and
-24PHB dry shielded canister (DSC) designs. The NUHOMS[supreg]-24PTH
System consists of new or modified components: (1) The -24PTH DSC; (2)
a new -24PTH DSC basket design; (3) a modified horizontal storage
module (HSM), designated the HSM-H; and (4) a modified transfer cask
(TC), designated the OS 197FC TC. The NUHOMS[supreg]-24PTH System is
designed to store fuel with maximum average burnup of up to 62
gigawatts-day/metric ton of uranium (GWd/MTU); maximum average initial
enrichment of 5.0 weight percent; minimum cooling time of 3.0 years;
and maximum heat load of 40.8 kilowatts (kW) per DSC. TS 1.2.18 and
Table 1-1l are augmented to restrict the -24PTH DSC basket heat loading
patterns to those analyzed in the Safety Analysis Report (SAR), and TS
1.2.17c is revised to delete the use of air for blowdown of the -24PTH
DSC before drying operations. The changes to the -32PT and -24PHB
systems include: (1) Revising the -32PT DSC Fuel Specification and Fuel
Qualification Tables to include low enrichment and reconstituted fuel;
(2) revising the -32PT DSC Fuel Specification Tables to show minimum
boron loading concentration; (3) expanding the authorized contents for
the -24PHB DSC; (4) revising the TC/DSC handling and lifting height
specifications in TS 1.2.10 and 1.2.13; and (5) clarifying DSC surface
contamination actions in TS 1.2.12. No other changes to the
Standardized NUHOMS[supreg] System cask design were requested in this
application. The NRC staff performed a detailed safety evaluation of
the proposed CoC amendment request and found that an acceptable safety
margin is maintained. In addition, the NRC staff has determined that
there continues to be reasonable assurance that public health and
safety and the environment will be adequately protected.
This direct final rule revises the Standardized NUHOMS[supreg]
System cask design listing in Sec. 72.214 by adding Amendment No. 8 to
CoC No. 1004. 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. 8.
The amended Standardized 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. 1004 is revised by adding the effective date of
Amendment Number 8.
Procedural Background
On May 25, 2005, a direct final rule (70 FR 29931) and companion
proposed rule (70 FR 30015) were published in the Federal Register, to
revise the cask system listing for the TN Standardized NUHOMS[supreg]
System, by adding Amendment No. 8 to the list of approved spent fuel
storage casks in 10 CFR 72.214. After the rules were published, staff
became aware of needed changes in the TS associated with the CoC, and
on July 15, 2005, the NRC withdrew the direct final rule (70 FR 40879)
and the proposed rule (70 FR 40924). This direct final rule includes
the original Amendment No. 8 changes, the revised TS 1.2.17c and
1.2.18, Table 1-1l, and additional changes, as discussed above. These
additional changes were originally to be addressed as a subsequent
amendment. However, the withdrawal of the May 25, 2005, package allowed
the staff to combine this information into Amendment No. 8. This
results in a more effective and efficient use of resources.
This rule is limited to the changes contained in Amendment No. 8 to
CoC No. 1004 and does not include other aspects of the Standardized
NUHOMS[supreg] System 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 December 5, 2005. However, if the NRC receives significant
adverse comments by October 20, 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. 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.
These comments will be addressed in a subsequent final rule. The
NRC will not initiate a second comment period on this action.
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 revises the
Standardized NUHOMS[supreg] System cask design listed in Sec. 72.214
(List of NRC-approved spent fuel storage cask designs). This action
does not constitute the establishment of a standard that 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''
[[Page 55025]]
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 is not a major Federal action significantly
affecting the quality of the human environment and, therefore, an
environmental impact statement is not required. The rule amends the CoC
for the Standardized 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 adds
a new spent fuel storage and transfer system, designated the
NUHOMS[supreg]-24PTH System, and modifies the NUHOMS[supreg]-32PT and -
24PHB DSC designs. The NUHOMS[supreg]-24PTH System consists of new or
modified components: (1) The -24PTH DSC; (2) a new -24PTH DSC basket
design; (3) a modified horizontal storage module, designated the HSM-H;
and (4) a modified transfer cask, designated the OS 197FC TC. The
NUHOMS[supreg]-24PTH System is designed to store fuel with maximum
average burnup of up to 62 GWd/MTU; maximum average initial enrichment
of 5.0 weight percent; minimum cooling time of 3.0 years; and maximum
heat load of 40.8 kW per DSC. TS 1.2.18 and Table 1-1l are augmented to
restrict the -24PTH DSC basket heat loading patterns to those analyzed
in the SAR, and TS 1.2.17c is revised to delete the use of air for
blowdown of the -24PTH DSC before drying operations. The changes to the
-32PT and -24PHB systems include: (1) Revising the -32PT DSC Fuel
Specification and Fuel Qualification Tables to include low enrichment
and reconstituted fuel; (2) revising the -32PT DSC Fuel Specification
Tables to show minimum boron loading concentration; (3) expanding the
authorized contents for the -24PHB DSC; (4) revising the TC/DSC
handling and lifting height specifications in TS 1.2.10 and 1.2.13; and
(5) clarifying DSC surface contamination actions in TS 1.2.12. The EA
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 EA 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, 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 December 22, 1994 (59 FR 65898), the NRC
issued an amendment to part 72 that approved the Standardized
NUHOMS[supreg] System (NUHOMS[supreg]-24P and -52B) by adding it to the
list of NRC-approved cask designs in Sec. 72.214. Amendments 3, 5, and
6, respectively, added the -61BT, -32PT, and -24PHB designs to the
Standardized NUHOMS[supreg] System. On September 19, 2003, and as
supplemented on January 22, April 21, May 28, July 6, August 16,
September 17, September 23, October 8, October 11, October 26, November
29, 2004, and January 14, March 15, June 10, and July 20, 2005, the
certificate holder, TN, submitted an application to the NRC to amend
CoC No. 1004 to add a new spent fuel storage and transfer system,
designated the NUHOMS[supreg]-24PTH System, and to modify the
NUHOMS[supreg] -32PT and -24PHB DSC designs. The NUHOMS[supreg]-24PTH
System consists of new or modified components: (1) The -24PTH DSC; (2)
a new -24PTH DSC basket design; (3) a modified horizontal storage
module, designated the HSM-H; and (4) a modified transfer cask,
designated the OS 197FC TC. The NUHOMS[supreg]-24PTH System is designed
to store fuel with maximum average burnup of up to 62 GWd/MTU; maximum
average initial enrichment of 5.0 weight percent; minimum cooling time
of 3.0 years; and maximum heat load of 40.8 kW per DSC. TS 1.2.18 and
Table 1-1l are augmented to restrict the -24PTH DSC basket heat loading
patterns to those analyzed in the SAR, and TS 1.2.17c is revised to
delete the use of air for blowdown of the -24PTH DSC prior to drying
operations. The changes to the -32PT and -24PHB systems include: (1)
Revising the -32PT DSC Fuel Specification and Fuel Qualification Tables
to include low enrichment and reconstituted fuel; (2) revising the -
32PT DSC Fuel Specification Tables to show minimum boron loading
concentration; (3) expanding the authorized contents for the -24PHB
DSC; (4) revising the TC/DSC handling and lifting height specifications
in TS 1.2.10 and 1.2.13; and (5) clarifying DSC surface contamination
actions in TS 1.2.12.
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
[[Page 55026]]
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.
Congressional Review Act
In accordance with the Congressional Review Act of 1996, the NRC
has determined that this action is not a major rule and has verified
this determination with the Office of Information and Regulatory
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 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, 2224 (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 1004 is revised to read
as follows:
Sec. 72.214 List of approved spent fuel storage casks.
* * * * *
Certificate Number: 1004.
Initial Certificate Effective Date: January 23, 1995.
Amendment Number 1 Effective Date: April 27, 2000.
Amendment Number 2 Effective Date: September 5, 2000.
Amendment Number 3 Effective Date: September 12, 2001.
Amendment Number 4 Effective Date: February 12, 2002.
Amendment Number 5 Effective Date: January 7, 2004.
Amendment Number 6 Effective Date: December 22, 2003.
Amendment Number 7 Effective Date: March 2, 2004.
Amendment Number 8 Effective Date: December 5, 2005.
SAR Title: Final Safety Analysis Report for the Standardized
NUHOMS[supreg] Horizontal Modular Storage System for Irradiated Nuclear
Fuel.
Docket Number: 72-1004.
Certificate Expiration Date: January 23, 2015.
Model Number: NUHOMS[supreg]-24P, -52B, -61BT, -32PT, -24PHB, and -
24PTH.
* * * * *
Dated at Rockville, Maryland, this 1st day of September 2005.
For the Nuclear Regulatory Commission.
Luis A. Reyes,
Executive Director for Operations.
[FR Doc. 05-18662 Filed 9-19-05; 8:45 am]
BILLING CODE 7590-01-P
