List of Approved Spent Fuel Storage Casks: HI-STORM 100 Revision 5, 33291-33294 [E8-13190]

Agencies

• NUCLEAR REGULATORY COMMISSION

[Federal Register Volume 73, Number 114 (Thursday, June 12, 2008)]
[Rules and Regulations]
[Pages 33291-33294]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E8-13190]



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Federal Register / Vol. 73, No. 114 / Thursday, June 12, 2008 / Rules 
and Regulations

[[Page 33291]]



NUCLEAR REGULATORY COMMISSION

10 CFR Part 72

RIN 3150-AI24
[NRC-2008-0013]


List of Approved Spent Fuel Storage Casks: HI-STORM 100 Revision 
5

AGENCY: Nuclear Regulatory Commission.

ACTION: Final rule.

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

SUMMARY: The Nuclear Regulatory Commission (NRC) is amending its 
regulations by revising the Holtec International HI-STORM 100 cask 
system listing within the ``List of approved spent fuel storage casks'' 
to include Amendment No. 5 to Certificate of Compliance (CoC) Number 
1014. Amendment No. 5 includes deletion of the requirement to perform 
thermal validation tests on thermal systems; an increase in the design 
basis maximum decay heat loads, namely, to 34 kilowatts (kW) for 
uniform loading and 36.9 kW for regionalized loading, and introduction 
of a new decay heat regionalized scheme; an increase in the maximum 
fuel assembly weight for boiling water reactor fuel in the Multi-
Purpose Canister (MPC)-68 from 700 to 730 pounds; an increase in the 
maximum fuel assembly weight of up to 1,720 pounds for assemblies not 
requiring spacers, otherwise 1,680 pounds; changes to the assembly 
characteristics of 16 x 16 pressurized water reactor fuel assemblies to 
be qualified for storage in the HI-STORM 100 cask system; a change in 
the fuel storage locations in the MPC-32 for fuel with axial power 
shaping rod assemblies and in the fuel storage locations in the MPC-24, 
MPC-24E, and the MPC-32 for fuel with control rod assemblies, rod 
cluster control assemblies, and control element assemblies; elimination 
of the restriction that fuel debris can only be loaded into the MPC-
24EF, MPC-32F, MPC-68F, and MPC-68FF canisters; introduction of a 
requirement that all MPC confinement boundary components and any MPC 
components exposed to spent fuel pool water or the ambient environment 
be made of stainless steel or, for MPC internals, neutron absorber or 
aluminum; the addition of a threshold heat load below which operation 
of the Supplemental Cooling System would not be required and 
modification of the design criteria to simplify the system; minor 
editorial changes to include clarification of the description of 
anchored casks, correction of typographical/editorial errors, 
clarification of the definitions of loading operations, storage 
operations, transport operations, unloading operations, cask loading 
facility, and transfer cask in various locations throughout the CoC and 
Final Safety Analysis Report; and modification of the definition of 
non-fuel hardware to include the individual parts of the items defined 
as non-fuel hardware. This final rule allows the holders of power 
reactor operating licenses to store spent fuel in this approved cask as 
specified in the revised conditions under the NRC's general license 
provisions.

DATES: The final rule is effective on July 14, 2008.

ADDRESSES: Publicly available documents related to this rulemaking may 
be viewed electronically at https://www.regulations.gov [Docket ID NRC-
2008-0013] and on the public computers located at the NRC's Public 
Document Room (PDR), Room O-1F21, One White Flint North, 11555 
Rockville Pike, Rockville, MD. The PDR reproduction contractor will 
copy documents for a fee.
    Publicly available documents created or received at the NRC are 
available electronically at the NRC's Electronic Reading Room at http:/
/www.nrc.gov/NRC/reading-rm/adams.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 any 
problems in accessing the documents located in ADAMS, contact the NRC 
PDR Reference staff at (800) 397-4209, (301) 415-4737, or by e-mail to 
pdr.resource@nrc.gov.

FOR FURTHER INFORMATION CONTACT: Jayne M. McCausland, Office of Federal 
and State Materials and Environmental Management Programs, U.S. Nuclear 
Regulatory Commission, Washington, DC 20555-0001, telephone (301) 415-
6219, e-mail Jayne.McCausland@nrc.gov.

SUPPLEMENTARY INFORMATION:

Background

    Section 218(a) of the Nuclear Waste Policy Act of 1982 (NWPA), as 
amended, 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 May 
1, 2000 (65 FR 25241), that approved the HI-STORM 100 cask system 
design, and added it to the list of NRC-approved cask designs in 10 CFR 
72.214 as Certificate of Compliance Number (CoC No.) 1014.

Discussion

    On December 30, 2004, the certificate holder, Holtec International 
(Holtec) submitted an application to the NRC that requested an 
amendment to CoC

[[Page 33292]]

No. 1014. The amendment principally included changes to increase the 
design basis maximum decay heat loads of the HI-STORM 100 cask system 
and add a new underground storage configuration, designated the HI-
STORM 100U, to the CoC. On November 29, 2006, Holtec withdrew the 
portion of the application that added the HI-STORM 100U to the CoC. The 
application, as modified by the December 22, 2006, Revision 2, 
submittal, and as supplemented on March 20, 2007, March 30, 2007, May 
4, 2007, May 22, 2007, June 15, 2007, July 17, 2007, and September 6, 
2007, requested changes to the CoC, the Technical Specifications (TS), 
and the Final Safety Analysis Report (FSAR), to modify the HI-STORM 100 
cask system. Specifically, the proposed changes included deletion of 
the requirement to perform thermal validation tests on thermal systems; 
an increase in the design basis maximum decay heat loads, namely, to 34 
kW for uniform loading and 36.9 kW for regionalized loading, and 
introduction of a new decay heat regionalized scheme; increase in the 
maximum fuel assembly weight for boiling water reactor fuel in the MPC-
68 from 700 to 730 pounds; an increase in the maximum fuel assembly 
weight of up to 1,720 pounds for assemblies not requiring spacers, 
otherwise 1,680 pounds; changes to the assembly characteristics of 
16x16 pressurized water reactor (PWR) fuel assemblies to be qualified 
for storage in the HI-STORM 100 cask system; a change in the fuel 
storage locations in the MPC-32 for fuel with axial power shaping rod 
assemblies (APSRAs) and in the fuel storage locations in the MPC-24, 
MPC-24E, and the MPC-32 for fuel with control rod assemblies (CRAs), 
rod cluster control assemblies (RCCAs), and control element assemblies 
(CEAs); elimination of the restriction that fuel debris can only be 
loaded into the MPC-24EF, MPC-32F, MPC-68F, and MPC-68FF canisters; 
introduction of a requirement that all MPC confinement boundary 
components and any MPC components exposed to spent fuel pool water or 
the ambient environment be made of stainless steel or, for MPC 
internals, neutron absorber or aluminum; the addition of a threshold 
heat load below which operation of the Supplemental Cooling System 
(SCS) would not be required and modification of the design criteria to 
simplify the system; minor editorial changes to include clarification 
of the description of anchored casks, correction of typographical/
editorial errors, clarification of the definitions of loading 
operations, storage operations, transport operations, unloading 
operations, cask loading facility, and transfer cask in various 
locations throughout the CoC and the FSAR; and modification of the 
definition of non-fuel hardware to include the individual parts of the 
items defined as non-fuel hardware.
    No other changes to the HI-STORM 100 cask system 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.
    The NRC published a direct final rule (72 FR 74162; December 31, 
2007) and the companion proposed rule (72 FR 74209; December 31, 2007) 
to amend the HI-STORM 100 cask system listing in 10 CFR 72.214 to 
include the changes requested by Holtec as Amendment No. 5 to CoC No. 
1014. The comment period ended on January 30, 2008. One comment letter 
was received on the proposed rule. The comment contained within the 
letter was considered to be significant and adverse and warranted 
withdrawal of the direct final rule. A notice of withdrawal was 
published in the Federal Register on March 12, 2008 (73 FR 13071). 
Additionally, the NRC staff is amending the CoC to remove the word 
``approximate'' from the weight designation of a loaded transfer cask, 
as discussed in the Summary of Public Comments on the Proposed Rule 
Section of this document. No changes were made in the TS or the safety 
evaluation report (SER) as a result of the comment.
    The NRC finds that the Holtec HI-STORM cask system, as designed and 
when fabricated and used under the conditions specified in its CoC, 
meets the requirements of 10 CFR Part 72. Thus, use of the Holtec HI-
STORM cask system, as approved by the NRC, will provide adequate 
protection of public health and safety and the environment. With this 
final rule, the NRC is approving the use of the Holtec HI-STORM 100 
cask system under the general license in 10 CFR Part 72, Subpart K, by 
holders of power reactor operating licenses under 10 CFR Part 50. 
Simultaneously, the NRC is issuing a final SER and CoC that will be 
effective on July 14, 2008. Single copies of the CoC and SER are 
available for public inspection and/or copying for a fee at the NRC 
Public Document Room, O-1F21, One White Flint North, 11555 Rockville 
Pike, Rockville, MD.

Discussion of Amendments by Section

Section 72.214 List of Approved Spent Fuel Storage Casks

    Certificate No. 1014 is revised by adding the effective date of 
Amendment Number 5.

Summary of Public Comments on the Proposed Rule

    The NRC received one comment letter on the proposed rule. Copies of 
the public comment letter are available for review in the NRC's Public 
Document Room, O-1F21, One White Flint North, 11555 Rockville Pike, 
Rockville, MD, and on https://www.regulations.gov. A review of the 
comment and the NRC staff's response follows:
    Comment: The commenter questioned the use of the word 
``approximate'' in relation to the maximum weight of a loaded transfer 
cask, stating that the actual weight of the transfer cask can be 
somewhat higher than 100 or 125 tons and still comply with the CoC. The 
commenter further noted that exceeding these maximum weight values 
would place the cask into an unanalyzed condition, thus raising a 
safety issue. The commenter stated that the NRC ``needs to specify a 
numerical range which would be considered `approximate' in order for 
the cask user to make a determination of compliance with the CoC and 
when NRC approval would be required for the heavier transfer cask.'' 
The commenter recommended deletion of the word ``approximate.''
    Response: The NRC staff agrees with the comment and has removed the 
word ``approximate'' from Section 1.b of the CoC. No changes are made 
to the SER or TS as a result of the comment.
    In addition, two minor typographical errors identified by Holtec in 
Appendix A of the CoC, i.e., Table 3-1 and TS 3.1.2, have been 
corrected.

Summary of Final Revisions

    Section 1.b. of the CoC has been revised to remove the word 
``approximate'' from the description of the weight designation of a 
loaded transfer cask during any loading, unloading, or transfer 
operation. In addition, two typographical errors have been corrected in 
Appendix A, Table 3-1 and TS 3.1.2. No changes to the SER are required 
as a result of these changes.

Voluntary Consensus Standards

    The National Technology Transfer and Advancement Act of 1995 (Pub. 
L. 104-113) requires that Federal agencies use technical standards that 
are developed or adopted by voluntary consensus standards bodies unless 
the

[[Page 33293]]

use of such a standard is inconsistent with applicable law or otherwise 
impractical. In this final rule, the NRC is revising the HI-ndash;STORM 
100 cask system design listed in 10 CFR 72.214 (List of NRC-approved 
spent fuel storage cask designs). This action does not constitute the 
establishment of a standard that contains generally applicable 
requirements.

Agreement State Compatibility

    Under the ``Policy Statement on Adequacy and Compatibility of 
Agreement State Programs'' approved by the Commission on June 30, 1997, 
and published in the Federal Register on September 3, 1997 (62 FR 
46517), this rule is classified as Compatibility Category ``NRC.'' 
Compatibility is not required for Category ``NRC'' regulations. The NRC 
program elements in this category are those that relate directly to 
areas of regulation reserved to the NRC by the Atomic Energy Act of 
1954 (AEA), as amended, 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.

Finding of No Significant Environmental Impact: Availability

    Under the National Environmental Policy Act of 1969, as amended, 
and the NRC regulations in Subpart A of 10 CFR Part 51, the NRC has 
determined that this rule, if adopted, would not be a major Federal 
action significantly affecting the quality of the human environment 
and, therefore, an environmental impact statement is not required. This 
final rule amends the CoC for the HI-STORM 100 cask 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. 
Amendment No. 5 modifies the present cask system design by the deletion 
of the requirement to perform thermal validation tests on thermal 
systems; an increase in the design basis maximum decay heat loads, 
namely, to 34 kW for uniform loading and 36.9 kW for regionalized 
loading, and introduction of a new decay heat regionalized scheme; an 
increase in the maximum fuel assembly weight for boiling water reactor 
fuel in the MPC-68 from 700 to 730 pounds; an increase in the maximum 
fuel assembly weight of up to 1,720 pounds for assemblies not requiring 
spacers, otherwise 1,680 pounds; changes in the assembly 
characteristics of 16x16 pressurized water reactor fuel assemblies to 
be qualified for storage in the HI-STORM 100 cask system; a change in 
the fuel storage locations in the MPC-32 for fuel with APSRAs and the 
fuel storage locations in the MPC-24, MPC-24E, and the MPC-32 for fuel 
with CRAs, RCCAs, and CEAs; elimination of the restriction that fuel 
debris can only be loaded into the MPC-24EF, MPC-32F, MPC-68F, and MPC-
68FF canisters; introduction of a requirement that all MPC confinement 
boundary components and any MPC components exposed to spent fuel pool 
water or the ambient environment be made of stainless steel or, for MPC 
internals, neutron absorber or aluminum; the addition of a threshold 
heat load below which operation of the SCS would not be required and 
modification of the design criteria to simplify the system; minor 
editorial changes to include clarification of the description of 
anchored casks, correction of typographical/editorial errors, 
clarification of the definitions of loading operations, storage 
operations, transport operations, unloading operations, cask loading 
facility, and transfer cask in various locations throughout the CoC and 
FSAR; and modification of the definition of non-fuel hardware to 
include the individual parts of the items defined as non-fuel hardware. 
In addition, in CoC Section 1.b., the word ``approximate'' is removed 
from the description of the weight designation of a loaded spent fuel 
storage cask during any loading, unloading, or transfer operation.
    The Environmental Assessment (EA) and finding of no significant 
impact on which this determination is based are available for 
inspection at the NRC Public Document Room, O-1F21, One White Flint 
North, 11555 Rockville Pike, Rockville, MD. Single copies of the EA and 
finding of no significant impact are available from Jayne M. 
McCausland, Office of Federal and State Materials and Environmental 
Management Programs, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001, telephone (301) 415-6219, e-mail Jayne.McCausland@nrc.gov.

Paperwork Reduction Act Statement

    This 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 10 CFR 72.214. On May 1, 2000 (65 FR 25241), the NRC 
issued an amendment to Part 72 that approved the HI-STORM 100 cask 
design by adding it to the list of NRC-approved cask designs in 10 CFR 
72.214. On December 30, 2004, the certificate holder, Holtec, submitted 
an application to the NRC that requested an amendment to CoC No. 1014. 
The amendment principally included changes to increase the design basis 
maximum decay heat loads of the HI-STORM 100 cask system and add a new 
underground storage configuration, designated the HI-STORM 100U, to the 
CoC. On November 29, 2006, Holtec withdrew the portion of the 
application that would have added the HI-STORM 100U to the CoC. The 
application, as modified on December 22, 2006 (Revision 2), and as 
supplemented on March 20, 2007, March 30, 2007, May 4, 2007, May 22, 
2007, June 15, 2007, July 17, 2007, and September 6, 2007, requested 
changes to the CoC, the TS, and the FSAR to modify the HI-STORM 100 
cask system.
    Specifically, the proposed changes included deletion of the 
requirement to perform thermal validation tests on thermal systems; an 
increase in the design basis maximum decay heat loads, namely, to 34 kW 
for uniform loading and 36.9 kW for regionalized loading, and 
introduction of a new decay heat regionalized scheme; increase in the 
maximum fuel assembly weight for boiling-water reactor fuel in the MPC-
68 from 700 to 730 pounds; an increase in the maximum fuel assembly 
weight of up to 1,720 pounds for assemblies not requiring spacers, 
otherwise 1,680 pounds; changes to the assembly characteristics of 
16x16 pressurized water reactor fuel assemblies to be

[[Page 33294]]

qualified for storage in the HI-STORM 100 cask system; a change in the 
fuel storage locations in the MPC-32 for fuel with APSRAs and in the 
fuel storage locations in the MPC-24, MPC-24E, and the MPC-32 for fuel 
with CRAs, RCCAs, and CEAs; elimination of the restriction that fuel 
debris can only be loaded into the MPC-24EF, MPC-32F, MPC-68F, and MPC-
68FF canisters; introduction of a requirement that all MPC confinement 
boundary components and any MPC components exposed to spent fuel pool 
water or the ambient environment be made of stainless steel or, for MPC 
internals, neutron absorber or aluminum; the addition of a threshold 
heat load below which operation of the SCS would not be required and 
modification of the design criteria to simplify the system; minor 
editorial changes to include clarification of the description of 
anchored casks, correction of typographical/editorial errors, 
clarification of the definitions of loading operations, storage 
operations, transport operations, unloading operations, cask loading 
facility, and transfer cask in various locations throughout the CoC and 
the FSAR; and modification of the definition of non-fuel hardware to 
include the individual parts of the items defined as non-fuel hardware. 
The alternative to this action is to withhold approval of this amended 
cask system design. Withholding approval, in the absence of any safety 
reason for doing so, would not comply with the requirements of sections 
218(a) and 133 of the Nuclear Waste Policy Act.
    Approval of the final rule is consistent with previous NRC actions. 
Further, the final rule will have no adverse effect on public health 
and safety. This 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 final rule are commensurate with the NRC's 
responsibilities for public health and safety and the common defense 
and security. No other available alternative is believed to be as 
satisfactory, and thus, this action is recommended.

Regulatory Flexibility Certification

    Under the Regulatory Flexibility Act of 1980 (5 U.S.C. 605(b)), the 
NRC certifies that this rule will not, if issued, have a significant 
economic impact on a substantial number of small entities. This final 
rule affects only the licensing and operation of nuclear power plants, 
independent spent fuel storage facilities, and Holtec. 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 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

    Under the Congressional Review Act of 1996, the NRC has determined 
that this action is not a major rule and has verified this 
determination with the Office of Information and Regulatory 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); sec. 651(e), Pub. L. 109-58, 119 Stat. 806-10 (42 U.S.C. 
2014, 2021, 2021b, 2111).
    Section 72.44(g) also issued under secs. 142(b) and 148(c), (d), 
Pub. L. 100-203, 101 Stat. 1330-232, 1330-236 (42 U.S.C. 10162(b), 
10168(c), (d)). Section 72.46 also issued under sec. 189, 68 Stat. 
955 (42 U.S.C. 2239); sec. 134, Pub. L. 97-425, 96 Stat. 2230 (42 
U.S.C. 10154). Section 72.96(d) also issued under sec. 145(g), Pub. 
L. 100-203, 101 Stat. 1330-235 (42 U.S.C. 10165(g)). Subpart J also 
issued under secs. 2(2), 2(15), 2(19), 117(a), 141(h), Pub. L. 97-
425, 96 Stat. 2202, 2203, 2204, 2222, 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 1014 is revised to read 
as follows:


Sec.  72.214  List of approved spent fuel storage casks.

* * * * *

Certificate Number: 1014.
Initial Certificate Effective Date: June 1, 2000.
Amendment Number 1 Effective Date: July 15, 2002.
Amendment Number 2 Effective Date: June 7, 2005.
Amendment Number 3 Effective Date: May 29, 2007.
Amendment Number 4 Effective Date: January 8, 2008.
Amendment Number 5 Effective Date: July 14, 2008.
SAR Submitted by: Holtec International.
SAR Title: Final Safety Analysis Report for the HI-STORM 100 Cask 
System.
Docket Number: 72-1014.
Certificate Expiration Date: June 1, 2020.
Model Number: HI-STORM 100.
* * * * *

    Dated at Rockville, Maryland, this 22nd day of May, 2008.

    For the Nuclear Regulatory Commission.
R.W. Borchardt,
Executive Director for Operations.
[FR Doc. E8-13190 Filed 6-11-08; 8:45 am]
BILLING CODE 7590-01-P