[Federal Register Volume 83, Number 243 (Wednesday, December 19, 2018)]
[Rules and Regulations]
[Page 65077]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2018-27436]


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NUCLEAR REGULATORY COMMISSION

10 CFR Part 72

[NRC-2018-0075]
RIN 3150-AK12


List of Approved Spent Fuel Storage Casks: NAC International NAC-
UMS[supreg] Universal Storage System, Certificate of Compliance No. 
1015, Amendment No. 6

AGENCY: Nuclear Regulatory Commission.

ACTION: Direct final rule; confirmation of effective date.

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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is confirming the 
effective date of January 7, 2019, for the direct final rule that was 
published in the Federal Register on October 22, 2018. This direct 
final rule amends the NRC's spent fuel storage regulations by revising 
the NAC International NAC-UMS[supreg] listing within the ``List of 
approved spent fuel storage casks'' to include Amendment No. 6 to 
Certificate of Compliance No. 1015. Amendment No. 6 revises the 
technical specifications of the certificate of compliance to: Remove a 
redundant requirement for inspection of the concrete cask and canister; 
revise a limiting condition of operation for heat removal to clarify 
that ``LCO not met'' means that the concrete heat removal system is 
inoperable; remove an inspection requirement that is already covered by 
limiting condition of operation surveillance requirements for off-
normal, accident, or natural phenomenon events; and clarify that 
``immediate'' restoration of a concrete cask's heat removal 
capabilities means ``within the design-basis time limit'' in Section 
11.2.13 of the final safety analysis report, ``or within the time limit 
for a less than design-basis heat load case, as evaluated.'' Amendment 
No. 6 also clarifies that a limiting condition of operation for loaded 
cask surface dose rates applies prior to storage conditions, when dose 
rates will be highest.

DATES: Effective date: The effective date of January 7, 2019, for the 
direct final rule published October 22, 2018 (83 FR 53159), is 
confirmed.

ADDRESSES: Please refer to Docket ID NRC-2018-0075 when contacting the 
NRC about the availability of information for this action. You may 
obtain publicly-available information related to this action by any of 
the following methods:
    <bullet> Federal Rulemaking Website: Go to http://www.regulations.gov and search for Docket ID NRC-2018-0075. Address 
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: <a href="/cdn-cgi/l/email-protection#591a382b3635771e383535383e313c2b19372b3a773e362f"><span class="__cf_email__" data-cfemail="733012011c1f5d34121f1f12141b1601331d01105d141c05">[email protected]</span></a>. For technical questions, contact 
the individuals listed in the FOR FURTHER INFORMATION CONTACT section 
of this document.
    <bullet> NRC's Agencywide Documents Access and Management System 
(ADAMS): You may obtain publicly-available documents online in the 
ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``Begin Web-based ADAMS 
Search.'' For problems with ADAMS, please contact the NRC's Public 
Document Room (PDR) reference staff at 1-800-397-4209, 301-415-4737, or 
by email to <a href="/cdn-cgi/l/email-protection#760612045804130519030415133618041558111900"><span class="__cf_email__" data-cfemail="4a3a2e3864382f39253f38292f0a243829642d253c">[email protected]</span></a>. The proposed amendment to the 
certificate, the proposed Appendices A and B to the technical 
specifications, and preliminary safety evaluation report are available 
in ADAMS under Accession No. ML18088A169. The final amendment to the 
certificate, final appendices to the technical specifications, and 
final safety evaluation report can also be viewed in ADAMS under 
Accession No. ML18333A232.
    <bullet> NRC's PDR: You may examine and purchase copies of public 
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555 
Rockville Pike, Rockville, Maryland 20852.

FOR FURTHER INFORMATION CONTACT: Bernard H. White, Office of Nuclear 
Material Safety and Safeguards; telephone: 301-415-6577; email: 
<a href="/cdn-cgi/l/email-protection#2b694e59454a594f057c43425f4e6b455948054c445d"><span class="__cf_email__" data-cfemail="f9bb9c8b97988b9dd7ae91908d9cb9978b9ad79e968f">[email protected]</span></a> or Robert D. MacDougall, Office of Nuclear 
Material Safety and Safeguards; telephone: 301-415-5175; email: 
<a href="/cdn-cgi/l/email-protection#98caf7fafdeaecb6d5f9fbdcf7edfff9f4f4d8f6eafbb6fff7ee"><span class="__cf_email__" data-cfemail="d082bfb2b5a2a4fe9db1b394bfa5b7b1bcbc90bea2b3feb7bfa6">[email protected]</span></a>. Both are staff of the U.S. Nuclear 
Regulatory Commission, Washington, DC 20555-0001.

SUPPLEMENTARY INFORMATION: On October 22, 2018 (83 FR 53159), the NRC 
published a direct final rule amending its regulations in part 72 of 
title 10 of the Code of Federal Regulations by revising the NAC 
International NAC-UMS[supreg] listing within the ``List of approved 
spent fuel storage casks'' to include Amendment No. 6 to Certificate of 
Compliance No. 1015. Amendment No. 6 revises the technical 
specifications of the certificate of compliance to: Remove a redundant 
requirement for inspection of the concrete cask and canister; revise a 
limiting condition of operation for heat removal to clarify that ``LCO 
not met'' means that the concrete heat removal system is inoperable; 
remove an inspection requirement that is already covered by limiting 
condition of operation surveillance requirements for off-normal, 
accident, or natural phenomenon events; and clarify that ``immediate'' 
restoration of a concrete cask's heat removal capabilities means 
``within the design-basis time limit'' in Section 11.2.13 of the final 
safety analysis report, ``or within the time limit for a less than 
design-basis heat load case, as evaluated.'' Amendment No. 6 also 
clarifies that a limiting condition of operation for loaded cask 
surface dose rates applies prior to storage conditions, when dose rates 
will be highest. In the direct final rule, the NRC stated that if no 
significant adverse comments were received, the direct final rule would 
become effective on January 7, 2019. The NRC did not receive any 
comments on the direct final rule. Therefore, this direct final rule 
will become effective as scheduled.

    Dated at Rockville, Maryland, this 13th day of December 2018.

    For the Nuclear Regulatory Commission.
Cindy K. Bladey,
Chief, Regulatory Analysis and Rulemaking Support Branch, Division of 
Rulemaking, Office of Nuclear Material Safety and Safeguards.
[FR Doc. 2018-27436 Filed 12-18-18; 8:45 am]
BILLING CODE 7590-01-P


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