[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:
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: [email protected]. For technical questions, contact
the individuals listed in the FOR FURTHER INFORMATION CONTACT section
of this document.
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 [email protected]. 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.
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:
[email protected] or Robert D. MacDougall, Office of Nuclear
Material Safety and Safeguards; telephone: 301-415-5175; email:
[email protected]. 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]
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