[Federal Register Volume 70, Number 181 (Tuesday, September 20, 2005)]
[Rules and Regulations]
[Pages 55023-55026]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 05-18662]



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  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 If the rule is withdrawn, timely notice will be published in 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: [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, 
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 
[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 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 [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 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