[Federal Register Volume 66, Number 169 (Thursday, August 30, 2001)]
[Rules and Regulations]
[Pages 45749-45752]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 01-21934]


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NUCLEAR REGULATORY COMMISSION

10 CFR Part 72

RIN 3150-AG83


List of Approved Spent Fuel Storage Casks: NAC-MPC 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 NAC-MPC cask system listing within the ``List 
of Approved Spent Fuel Storage Casks'' to include Amendment No. 1 to 
Certificate of Compliance Number 1025. Amendment No. 1 will modify the 
present cask system design to permit a licensee to use an alternate 
fuel basket design with enlarged fuel tubes in corner locations; 
increase the operational time limits provided in the Technical 
Specifications (TS) for canister loading, closure, and transfer when 
canister heat loads are lower than design basis heat loads; revise the 
canister surface contamination limits in TS to maintain worker dose as 
low as is reasonably achievable (ALARA); and revise some drawings to 
reflect changes identified during cask and component fabrication under 
a general license.

DATES: The final rule is effective November 13, 2001, unless 
significant adverse comments are received by October 1, 2001. 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 If the rule is withdrawn, timely notice will be 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: Submit comments to: Secretary, U.S. Nuclear Regulatory 
Commission, Washington, DC 20555-0001, Attn: Rulemakings and 
Adjudications Staff. Deliver comments to 11555 Rockville Pike, 
Rockville, MD, between 7:30 a.m. and 4:15 p.m. on Federal workdays.
    Certain documents related to this rulemaking, as well as all public 
comments received on this rulemaking, may be viewed and downloaded 
electronically via the NRC's rulemaking website at http://ruleforum.llnl.gov. You may also provide comments via this website by 
uploading comments as files (any format) if your web browser supports 
that function. For information about the interactive rulemaking site, 
contact Ms. Carol Gallagher, (301) 415-5905; email [email protected].
    Certain documents related to this rule, including comments received 
by the NRC, may be examined at the NRC Public Document Room, 11555 
Rockville Pike, Rockville, MD. For more information, contact the NRC 
Public Document Room (PDR) Reference staff at 1-800-397-4209, 301-415-
4737 or by email to [email protected].
    Documents created or received at the NRC after November 1, 1999, 
are also available electronically at the NRC's Public Electronic 
Reading Room on the Internet at http://www.nrc.gov/NRC/ADAMS/index.html. From this site, the

[[Page 45750]]

public can gain entry into the NRC's Agencywide Documents Access and 
Management System (ADAMS), which provides text and image files of NRC's 
public documents. An electronic copy of the proposed Certificate of 
Compliance (CoC) and preliminary safety evaluation report (SER) can be 
found under ADAMS Accession No. ML 011380038. 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 email to [email protected].
    CoC No. 1025, the revised TS, and the underlying SER for Amendment 
No. 1, and the Environmental Assessment, are available for inspection 
at the NRC Public Document Room, 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, email [email protected]. 

FOR FURTHER INFORMATION CONTACT: Jayne M. McCausland, telephone (301) 
415-6219, email [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 March 
9, 2000 (65 FR 12444) that approved the NAC-MPC cask design and added 
it to the list of NRC-approved cask designs in Sec. 72.214 as 
Certificate of Compliance Number (CoC No.) 1025.

Discussion

    On September 29, 2000, and as supplemented on October 5, 2000, 
March 16, 2001, April 6, 2001, and July 27, 2001, NAC International, 
Inc., submitted an application and associated Safety Analysis Report to 
the NRC to amend CoC No.1025 to permit a Part 72 general licensee to: 
(1) Use an alternate fuel basket design with enlarged fuel tubes in 
corner locations; (2) increase the operational time limits provided in 
TS for canister loading, closure, and transfer when canister heat loads 
are lower than design basis heat loads; (3) revise the canister surface 
contamination limits in TS to maintain worker dose ALARA; and (4) 
revise some drawings to reflect changes identified during cask and 
component fabrication. No other changes to the NAC-MPC 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 the requested changes do not reduce the safety margin. In 
addition, the NRC staff has determined that the changes do not pose any 
increased risk to public health and safety.
    This direct final rule revises the NAC-MPC cask design listing in 
Sec. 72.214 by adding Amendment No. 1 to CoC No. 1025. The amendment 
consists of changes to TS 3.1.2, 3.1.3, 3.1.5, 3.1.6, 3.1.10, and 
3.2.2, as identified in the NRC staff's SER for Amendment No. 1.
    The amended NAC-MPC 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

72.214  List of Approved Spent Fuel Storage Casks

    Certificate No. 1025 is revised by adding the effective date of the 
initial certificate, and the effective date of Amendment Number 1. The 
CoC and the TS have been modified.

Procedural Background

    This rule is limited to the changes contained in Amendment 1 to CoC 
No. 1025 and does not include other aspects of the NAC-MPC 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 November 13, 2001. 
However, if the NRC receives significant adverse comments by October 1, 
2001, 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 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 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 staff to make a change 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 NAC-
MPC cask system design listed in Sec. 72.214 (List of approved spent 
fuel

[[Page 45751]]

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 NAC-MPC 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 cask system design to permit a Part 
72 licensee to: (1) Use an alternate fuel basket design with enlarged 
fuel tubes in corner locations; (2) increase the operational time 
limits provided in TS for canister loading, closure, and transfer when 
canister heat loads are lower than design basis heat loads; (3) revise 
the canister surface contamination limits in TS to maintain worker dose 
ALARA; and (4) revise some drawings to reflect changes identified 
during cask and component fabrication. The environmental assessment 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 environmental 
assessment 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

    If a means used to impose an information collection does not 
display a currently valid OMB control number, the NRC may not conduct 
or sponsor, and a person is not required to respond to, the information 
collection.

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 March 9, 2000 (65 FR 12444), the NRC 
subsequently issued an amendment to Part 72 that approved the NAC-MPC 
cask design by adding it to the list of NRC-approved cask designs in 
Sec. 72.214. On September 29, 2000, and as supplemented on October 5, 
2000, March 16, 2001, April 6, 2001, and July 27, 2001, NAC 
International, Inc., submitted an application and associated Safety 
Analysis Report to the NRC to amend CoC No.1025 to permit a Part 72 
general licensee to: (1) Use an alternate fuel basket design with 
enlarged fuel tubes in corner locations; (2) increase the operational 
time limits provided in TS for canister loading, closure, and transfer 
when canister heat loads are lower than design basis heat loads; (3) 
revise the canister surface contamination limits in TS to maintain 
worker dose ALARA; and (4) revise some drawings to reflect changes 
identified during cask and component fabrication.
    This direct final rule will revise the NAC-MPC cask design listing 
in Sec. 72.214 by adding Amendment No. 1 to CoC No. 1025. The amendment 
consists of changes to TS 3.1.2, 3.1.3, 3.1.5, 3.1.6, 3.1.10, and 
3.2.2, as identified in the NRC staff's SER for Amendment No. 1. 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 the above 
described 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 the above 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 
NAC International, Inc. 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.

[[Page 45752]]

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.

    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 AND HIGH-LEVEL RADIOACTIVE WASTE

    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).
    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).
    2. In Sec. 72.214, Certificate of Compliance 1025 is revised to 
read as follows:


Sec. 72.214  List of approved spent fuel storage casks.

* * * * *
Certificate Number: 1025.

Initial Certificate Effective Date: April 10, 2000.

Amendment Number 1 Effective Date: November 13, 2001.

SAR Submitted by: NAC International, Inc.

SAR Title: Final Safety Analysis Report for the NAC Multi-Purpose 
Canister System (NAC-MPC System).

Docket Number: 72-1025.

Certificate Expiration Date: April 10, 2020.

Model Number: NAC-MPC.
* * * * *

    Dated at Rockville, Maryland, this 20th day of August, 2001.

    For the Nuclear Regulatory Commission.
William D. Travers,
Executive Director for Operations.
[FR Doc. 01-21934 Filed 8-29-01; 8:45 am]
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