[Federal Register Volume 70, Number 100 (Wednesday, May 25, 2005)]
[Rules and Regulations]
[Pages 29931-29934]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 05-10389]


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NUCLEAR REGULATORY COMMISSION

10 CFR Part 72

RIN 3150-AH72


List of Approved Spent Fuel Storage Casks: Standardized 
NUHOMS[reg]-24P, -52B, -61BT, -32PT, -24PHB, and -24PTH 
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 Transnuclear, Inc., Standardized 
NUHOMS[reg] 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[reg] System CoC will modify the cask design by adding 
a new spent fuel storage and transfer system, designated the 
NUHOMS[reg]-24PTH System. The NUHOMS[reg]-24PTH 
System consists of new or modified components: The -24PTH dry shielded 
canister (DSC); a new -24PTH DSC basket design; a modified horizontal 
storage module (HSM), designated the HSM-H; and a modified transfer 
cask (TC), designated the OS 197FC TC. The NUHOMS[reg]-24PTH 
System is designed to store fuel with a maximum average burnup of up to 
62 gigawatts-day/metric ton of uranium; maximum average initial 
enrichment of 5.0 weight percent; minimum cooling time of 3.0 years; 
and maximum heat load of 40.8 kilowatts per DSC, under a general 
license.

DATES: The final rule is effective August 8, 2005, unless significant 
adverse comments are received by June 24, 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the rule is withdrawn, timely notice will be published in the Federal 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-AH72) 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

[[Page 29932]]

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, 
Technical Specifications (TS), and preliminary safety evaluation report 
(SER) can be found under ADAMS Accession No. ML050750211.
    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 
[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 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 65920), that approved the Standardized 
NUHOMS[reg] System (NUHOMS[reg]-24P and -52B) 
cask designs and added them to the list of NRC-approved cask designs in 
Sec.  72.214 as CoC No. 1004. Amendments 3, 5, and 6, respectively, 
added the -61BT, -32PT, -24PHB designs to the Standardized 
NUHOMS[reg] System.

Discussion

    On September 19, 2003, and as supplemented on January 22, July 6, 
August 16, September 17, and October 11, 2004; and January 14 and March 
15, 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[reg]-
24PTH System. The NUHOMS[reg]-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[reg]-24PTH System is designed to store fuel with a 
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. No other changes to the Standardized 
NUHOMS[reg] 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 is still reasonable assurance that public health and safety and 
the environment will be adequately protected.
    This direct final rule revises the Standardized 
NUHOMS[reg] 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[reg] 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

    This rule is limited to the changes contained in Amendment 8 to CoC 
No. 1004 and does not include other aspects of the Standardized 
NUHOMS[reg] 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 August 8, 2005. However, if the NRC receives significant 
adverse comments by June 24, 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

[[Page 29933]]

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 
Standardized NUHOMS[reg] 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'' regulations. The NRC 
program elements in this category are those that relate directly to 
areas of regulation reserved to the NRC by the Atomic Energy Act of 
1954, as amended (AEA), or the provisions of Title 10 of the Code of 
Federal Regulations. Although an Agreement State may not adopt program 
elements reserved to NRC, it may wish to inform its licensees of 
certain requirements via a mechanism that is consistent with the 
particular State's administrative procedure laws but does not confer 
regulatory authority on the State.

Plain Language

    The Presidential Memorandum dated June 1, 1998, entitled ``Plain 
Language in Government Writing,'' directed that the Government's 
writing be in plain language. The NRC requests comments on this direct 
final rule specifically with respect to the clarity and effectiveness 
of the language used. Comments should be sent to the address listed 
under the heading ADDRESSES above.

Finding of No Significant Environmental Impact: Availability

    Under the National Environmental Policy Act of 1969, as amended, 
and the NRC regulations in subpart A of 10 CFR part 51, the NRC has 
determined that this rule, if adopted, would not be a major Federal 
action significantly affecting the quality of the human environment 
and, therefore, an environmental impact statement is not required. The 
rule would amend the CoC for the Standardized NUHOMS[reg] 
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 add a new spent fuel storage and 
transfer system, designated the NUHOMS[reg]-24PTH System, to 
the Standardized NUHOMS[reg] System. The 
NUHOMS[reg]-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[reg]-24PTH System is designed to store fuel with a 
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. 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 
[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 December 22, 1994 (59 FR 65920), the NRC 
issued an amendment to Part 72 that approved the Standardized 
NUHOMS[reg] System (NUHOMS[reg]-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, -24PHB 
designs to the Standardized NUHOMS[reg] System. On September 
19, 2003, and as supplemented on January 22, July 6, August 16, 
September 17, and October 11, 2004; and January 14 and March 15, 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[reg]-24PTH System. The 
NUHOMS[reg]-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[reg]-24PTH System is designed to store fuel with a 
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.
    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

[[Page 29934]]

each utility would have to pursue an exemption.
    Approval of the direct final rule will eliminate this problem and 
is consistent with previous NRC actions. Further, the direct final rule 
will have no adverse effect on public health and safety. This direct 
final rule has no significant identifiable impact or benefit on other 
Government agencies. Based on this discussion of the benefits and 
impacts of the alternatives, the NRC concludes that the requirements of 
the direct final rule are commensurate with the NRC's responsibilities 
for public health and safety and the common defense and security. No 
other available alternative is believed to be as satisfactory, and 
thus, this action is recommended.

Regulatory Flexibility Certification

    In accordance with the Regulatory Flexibility Act of 1980 (5 U.S.C. 
605(b)), the NRC certifies that this rule will not, if issued, have a 
significant economic impact on a substantial number of small entities. 
This direct final rule affects only the licensing and operation of 
nuclear power plants, independent spent fuel storage facilities, and 
TN. The companies that own these plants do not fall within the scope of 
the definition of ``small entities'' set forth in the Regulatory 
Flexibility Act or the Small Business Size Standards set out in 
regulations issued by the Small Business Administration at 13 CFR part 
121.

Backfit Analysis

    The NRC has determined that the backfit rule (10 CFR 50.109 or 10 
CFR 72.62) does not apply to this direct final rule because this 
amendment does not involve any provisions that would impose backfits as 
defined. Therefore, a backfit analysis is not required.

Small Business Regulatory Enforcement Fairness Act

    In accordance with the Small Business Regulatory Enforcement 
Fairness Act of 1996, the NRC has determined that this action is not a 
major rule and has verified this determination with the Office of 
Information and Regulatory Affairs, Office of Management and Budget.

List of Subjects In 10 CFR Part 72

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


0
For the reasons set out in the preamble and under the authority of the 
Atomic Energy Act of 1954, as amended; the Energy Reorganization Act of 
1974, as amended; and 5 U.S.C. 552 and 553; the NRC is adopting the 
following amendments to 10 CFR Part 72.

PART 72--LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF 
SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-
RELATED GREATER THAN CLASS C WASTE

0
1. The authority citation for Part 72 continues to read as follows:

    Authority: Secs. 51, 53, 57, 62, 63, 65, 69, 81, 161, 182, 183, 
184, 186, 187, 189, 68 Stat. 929, 930, 932, 933, 934, 935, 948, 953, 
954, 955, as amended, sec. 234, 83 Stat. 444, as amended (42 U.S.C. 
2071, 2073, 2077, 2092, 2093, 2095, 2099, 2111, 2201, 2232, 2233, 
2234, 2236, 2237, 2238, 2282); sec. 274, Pub. L. 86-373, 73 Stat. 
688, as amended (42 U.S.C. 2021); sec. 201, as amended, 202, 206, 88 
Stat. 1242, as amended, 1244, 1246 (42 U.S.C. 5841, 5842, 5846); 
Pub. L. 95-601, sec. 10, 92 Stat. 2951 as amended by Pub. L. 102-
486, sec. 7902, 106 Stat. 3123 (42 U.S.C. 5851); sec. 102, Pub. L. 
91-190, 83 Stat. 853 (42 U.S.C. 4332); secs. 131, 132, 133, 135, 
137, 141, Pub. L. 97-425, 96 Stat. 2229, 2230, 2232, 2241, sec. 148, 
Pub. L. 100-203, 101 Stat. 1330-235 (42 U.S.C. 10151, 10152, 10153, 
10155, 10157, 10161, 10168); sec. 1704, 112 Stat. 2750 (44 U.S.C. 
3504 note).
    Section 72.44(g) also issued under secs. 142(b) and 148(c)), 
(d), Pub. L. 100-203, 101 Stat. 1330-232, 1330-236 (42 U.S.C. 
10162(b), 10168(c),(d)). Section 72.46 also issued under sec. 189, 
68 Stat. 955 (42 U.S.C. 2239); sec. 134, Pub. L. 97-425, 96 Stat. 
2230 (42 U.S.C. 10154). Section 72.96(d) also issued under sec. 
145(g), Pub. L. 100-203, 101 Stat. 1330-235 (42 U.S.C. 10165(g)). 
Subpart J also issued under secs. 2(2), 2(15), 2(19), 117(a), 
141(h), Pub. L. 97-425, 96 Stat. 2202, 2203, 2204, 2222, 2244 (42 
U.S.C. 10101, 10137(a), 10161(h)). Subparts K and L are also issued 
under sec. 133, 98 Stat. 2230 (42 U.S.C. 10153) and sec. 218(a), 96 
Stat. 2252 (42 U.S.C. 10198).


0
2. In Sec.  72.214, Certificate of Compliance 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: August 8, 2005.
    SAR Submitted by: Transnuclear, Inc.
    SAR Title: Final Safety Analysis Report for the Standardized 
NUHOMS[reg] 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 6 day of May, 2005.

    For the Nuclear Regulatory Commission.
Luis A. Reyes,
Executive Director for Operations.
[FR Doc. 05-10389 Filed 5-24-05; 8:45 am]
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