[Federal Register Volume 70, Number 38 (Monday, February 28, 2005)]
[Rules and Regulations]
[Pages 9504-9507]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 05-3739]


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NUCLEAR REGULATORY COMMISSION

10 CFR Part 72

RIN 3150-AH64


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

AGENCY: Nuclear Regulatory Commission.

ACTION: Direct final rule.

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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, 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the rule is withdrawn, timely notice will be published in the Federal 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: [email protected]. 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 http://ruleforum.llnl.gov. Address questions 
about our rulemaking Web site to Carol Gallagher (301) 415-5905; e-mail 
[email protected]. Comments can also be submitted via the Federal eRulemaking 
Portal http://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 http://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 http://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 [email protected]. 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 [email protected].

FOR FURTHER INFORMATION CONTACT: Jayne M. McCausland, telephone (301) 
415-6219, e-mail [email protected], 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

[[Page 9505]]

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 Holtec 
International HI-STORM 100 cask design and added it to the list of NRC-
approved cask designs in Sec.  72.214 as CoC No. 1014.

Discussion

    On March 4, 2002, and as supplemented on October 31, 2002; August 6 
and November 14, 2003; February 20, April 23, July 22, August 13, 
October 14, and December 3, 2004, the certificate holder, Holtec 
International, submitted an application to the NRC to amend CoC No. 
1014 to permit a Part 72 licensee to 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, changes in 
allowable fuel enrichments, and other changes to reflect current staff 
guidance and use of industry codes, under a general license. The 
specific changes requested in Amendment No. 2 to CoC No. 1014 are 
listed in the SER. No other changes to the HI-STORM 100 cask system 
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 is still reasonable assurance that 
public health and safety and the environment will be adequately 
protected.
    This direct final rule revises the HI-STORM 100 cask design listing 
in Sec.  72.214 by adding Amendment No. 2 to CoC No. 1014. 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. 2.
    The amended HI-STORM 100 cask 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. 1014 is revised by adding the effective date of 
Amendment Number 2.

Procedural Background

    This rule is limited to the changes contained in Amendment 2 to CoC 
No. 1014 and does not include other aspects of the HI-STORM 100 cask 
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 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. 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 would revise the HI-
STORM 100 cask 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 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. 
The amendment will modify the present

[[Page 9506]]

cask system 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, changes in allowable fuel enrichments, 
and other changes to reflect current NRC staff guidance and use of 
industry codes, under a general license. 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, email 
[email protected].

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 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 Sec.  72.214. On 
March 4, 2002, and as supplemented on October 31, 2002; August 6 and 
November 14, 2003; February 20, April 23, July 22, August 13, October 
14, and December 3, 2004, the certificate holder (Holtec International) 
submitted an application to the NRC to amend CoC No. 1014 to modify the 
present cask system 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, changes in allowable fuel enrichments, 
and other changes to reflect current staff guidance and use of industry 
codes under a general license.
    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 
Holtec International. 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 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).


[[Page 9507]]


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: May 16, 2005.
    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 14th day of February, 2005.

    For the Nuclear Regulatory Commission.
Luis A. Reyes,
Executive Director for Operations.
[FR Doc. 05-3739 Filed 2-25-05; 8:45 am]
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