List of Approved Spent Fuel Storage Casks: Holtec International HI-STORM 100 Multipurpose Canister Cask System, Certificate of Compliance No. 1014, Amendment Nos. 11 and 12, 4684-4685 [2019-02593]

Download as PDF 4684 Federal Register / Vol. 84, No. 33 / Tuesday, February 19, 2019 / Rules and Regulations ‘‘CONCRETE CASK Heat Removal System.’’ In the direct final rule, the NRC stated that if no significant adverse comments were received, the direct final rule would become effective on March 4, 2019. As described more fully in the direct final rule, 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. Because no significant adverse comments were received, the direct final rule will become effective as scheduled. Dated at Rockville, Maryland, this 12th day of February 2019. 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. 2019–02599 Filed 2–15–19; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION 10 CFR Part 72 [NRC–2018–0221] RIN 3150–AK18 List of Approved Spent Fuel Storage Casks: Holtec International HI–STORM 100 Multipurpose Canister Cask System, Certificate of Compliance No. 1014, Amendment Nos. 11 and 12 Nuclear Regulatory Commission. ACTION: Direct final rule; confirmation of effective date. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) is confirming the effective date of February 25, 2019, for the direct final rule that was published in the Federal Register on December 12, 2018. This direct final rule amended the NRC’s spent fuel storage regulations by revising the Holtec International HI– STORM 100 Multipurpose Canister Cask System (HI–STORM 100 System) listing within the ‘‘List of approved spent fuel storage casks’’ to include Amendment Nos. 11 and 12 to Certificate of Compliance No. 1014. Amendment Nos. 11 and 12 revise multiple items in the technical specifications for multipurpose canister models listed under Certificate of Compliance No. 1014; most of these revisions involve changes to the authorized contents. In addition, tkelley on DSKBCP9HB2PROD with RULES SUMMARY: VerDate Sep<11>2014 17:01 Feb 15, 2019 Jkt 247001 Amendment No. 11 makes several other editorial changes. DATES: The effective date of February 25, 2019, for the direct final rule published December 12, 2018 (83 FR 63794), is confirmed. ADDRESSES: Please refer to Docket ID NRC–2018–0221 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 https://www.regulations.gov and search for Docket ID NRC–2018–0221. Address questions about NRC dockets to Carol Gallagher; telephone: 301–415–3463; email: Carol.Gallagher@nrc.gov. 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 publiclyavailable documents online in the ADAMS Public Documents collection at https://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 pdr.resource@ nrc.gov. The proposed amendments to the certificate, the proposed changes to the technical specifications, and the preliminary safety evaluation reports are available in ADAMS for Amendment No. 11 under Accession No. ML18141A560 and Amendment No. 12 under Accession No. ML18087A055. The final amendments to the certificate, final changes to the technical specifications, and final safety evaluation reports can also be viewed in ADAMS under Accession No. ML18355A369. • 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: YenJu Chen, Office of Nuclear Material Safety and Safeguards; telephone: 301– 415–1018; email: Yen-Ju.Chen@nrc.gov or Vanessa Cox, Office of Nuclear Material Safety and Safeguards; telephone: 301–415–8342; email: Vanessa.Cox@nrc.gov. Both are staff of the U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001. SUPPLEMENTARY INFORMATION: On December 12, 2018 (83 FR 63794), the NRC published a direct final rule PO 00000 Frm 00008 Fmt 4700 Sfmt 4700 amending its regulations in part 72 of title 10 of the Code of Federal Regulations (10 CFR) to the HI–STORM 100 System listing within the ‘‘List of approved spent fuel storage casks’’ to include Amendment Nos. 11 and 12 to Certificate of Compliance No. 1014. Amendment Nos. 11 and 12 revise multiple items in the technical specifications for multi-purpose canister models listed under Certificate of Compliance No. 1014; most of these revisions involve changes to the authorized contents. In addition, Amendment No. 11 makes several other editorial changes. In the direct final rule, the NRC stated that if no significant adverse comments were received, the direct final rule would become effective on February 25, 2019. As described more fully in the direct final rule, 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. The NRC received two comments and has determined that they are not significant adverse comments. One comment questioned the short-term economic gains. As this rulemaking only addressed changes to the technical specifications for dry shielded canisters used to store nuclear waste on-site, the NRC determined this comment to be out of scope of this direct final rule. The second comment concerned specific casks used at a reactor site, a direct final rule for another storage cask, and another cask that is the subject of an NRC enforcement action. These issues are also outside the scope of this direct final rule. The second commenter also stated that the environmental assessment for this direct final rule did not consider the effects of certain natural phenomena. Pursuant to 10 CFR part 72, the NRC requires that an applicant for a spent fuel storage system provide the design bases, design criteria, and the margins of safety for the system in its safety analysis. The design bases, design criteria, and safety margins include consideration of applicable natural phenomena. In its review, the NRC determined that the cask system is designed to mitigate the effects of design basis accidents, including humaninduced and the most severe natural phenomena. Specifically, in considering design requirements for each accident condition, the NRC evaluates whether the design would prevent loss of confinement, shielding, and criticality control in the event of an accident. The NRC identified a broad range of natural E:\FR\FM\19FER1.SGM 19FER1 Federal Register / Vol. 84, No. 33 / Tuesday, February 19, 2019 / Rules and Regulations hazards and accidents that were considered in the environmental assessment for this direct final rule. Further, the safety evaluation report for the Holtec International HI–STORM 100 Cask System (ADAMS Accession No. ML003711865; May 4, 2000) identified all accident-level events and conditions, which are Design Events III and IV as defined in American National Standard Institute/American Nuclear Society 57.9–1984. These include natural phenomena and human-induced lowprobability events such as those listed in Comment 2. The NRC determined in the May 4, 2000, safety evaluation report that all potential safety consequences were considered. This direct final rule makes changes to the technical specifications of Certificate of Compliance No. 1014 for the HI–STORM 100 Cask System. However, this direct final rule makes limited and routine changes; it does not involve significant changes to the design or the fabrication of the cask system. The second comment does not raise specific safety concerns regarding the changes made in this direct final rule. The second comment did not propose a specific change or an addition that could be incorporated into this direct final rule and did not raise a relevant issue not previously addressed by the NRC. Accordingly, the second comment does not meet the criteria of a significant adverse comment. Because no significant adverse comments were received, this direct final rule will become effective as scheduled. Dated at Rockville, Maryland, this 12th day of February 2019. 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. 2019–02593 Filed 2–15–19; 8:45 am] BILLING CODE 7590–01–P DEPARTMENT OF TRANSPORTATION Federal Aviation Administration 14 CFR Part 39 tkelley on DSKBCP9HB2PROD with RULES [Docket No. FAA–2018–0647; Product Identifier 2017–SW–083–AD; Amendment 39–19557; AD 2019–03–05] RIN 2120–AA64 Airworthiness Directives; Bell Helicopter Textron Canada Limited Helicopters Federal Aviation Administration (FAA), DOT. AGENCY: VerDate Sep<11>2014 17:01 Feb 15, 2019 Jkt 247001 ACTION: Final rule. We are adopting a new airworthiness directive (AD) for Bell Helicopter Textron Canada Limited (Bell) Model 429 helicopters. This AD revises the life limit for the nose landing gear (NLG) assembly. This AD was prompted by revised airworthiness limitations determined by Bell. The actions of this AD are intended to prevent an unsafe condition on these products. DATES: This AD is effective March 26, 2019. ADDRESSES: For service information identified in this final rule, contact Bell Helicopter Textron Canada Limited, 12,800 Rue de l’Avenir, Mirabel, Quebec J7J1R4; telephone (450) 437–2862 or (800) 363–8023; fax (450) 433–0272; or at https://www.bellcustomer.com/files/. You may review the referenced service information at the FAA, Office of the Regional Counsel, Southwest Region, 10101 Hillwood Pkwy., Room 6N–321, Fort Worth, TX 76177. SUMMARY: Examining the AD Docket You may examine the AD docket on the internet at https:// www.regulations.gov by searching for and locating Docket No. FAA–2018– 0647; or in person at Docket Operations between 9 a.m. and 5 p.m., Monday through Friday, except Federal holidays. The AD docket contains this AD, the Transport Canada AD, the economic evaluation, any comments received, and other information. The street address for Docket Operations (phone: 800–647– 5527) is U.S. Department of Transportation, Docket Operations, M– 30, West Building Ground Floor, Room W12–140, 1200 New Jersey Avenue SE, Washington, DC 20590. FOR FURTHER INFORMATION CONTACT: Matt Fuller, Senior Aviation Safety Engineer, Safety Management Section, Rotorcraft Standards Branch, FAA, 10101 Hillwood Pkwy., Fort Worth, TX 76177; telephone (817) 222–5110; email matthew.fuller@faa.gov. SUPPLEMENTARY INFORMATION: Discussion On July 19, 2018, at 83 FR 34074, the Federal Register published our notice of proposed rulemaking (NPRM), which proposed to amend 14 CFR part 39 by adding an AD that would apply to Bell Model 429 helicopters with a NLG assembly part number (P/N) 429–336– 100–101 installed. The NPRM proposed to revise the life limit for the NLG assembly. The proposed requirements were intended to prevent fatigue failure of an NLG assembly, which could result PO 00000 Frm 00009 Fmt 4700 Sfmt 4700 4685 in subsequent damage to and loss of control of the helicopter. The NPRM was prompted by Canadian AD No. CF–2016–07, dated March 4, 2016, to correct an unsafe condition for Bell Model 429 helicopters with wheeled landing gear. Transport Canada, which is the aviation authority for Canada, issued its AD after Bell replaced the airworthiness limitations for the NLG main fitting to bell crank bolt P/N M084–20H125–101 and NLG main fitting P/N M084–20H011–107 with an airworthiness limitation for the next higher assembly, NLG assembly P/ N 429–336–100–101. According to Transport Canada, the NLG assembly’s life limit is reduced to 50,000 retirement index number (RIN) or 4,500 hours time-in-service. Transport Canada advises that failure to replace components prior to established airworthiness limitations could result in an unsafe condition. Comments We gave the public the opportunity to participate in developing this AD, but we received no comments on the NPRM. FAA’s Determination These helicopters have been approved by the aviation authority of Canada and are approved for operation in the United States. Pursuant to our bilateral agreement with Canada, Transport Canada, its technical representative, has notified us of the unsafe condition described in the Transport Canada AD. We are issuing this AD because we evaluated all information provided by Transport Canada and determined the unsafe condition exists and is likely to exist or develop on other helicopters of these same type designs and that air safety and the public interest require adopting the AD requirements as proposed. Differences Between This AD and the Transport Canada AD The Transport Canada AD applies to certain serial-numbered helicopters, whereas this AD applies to all Bell Model 429 helicopters with the affected NLG assembly installed. Related Service Information We reviewed Bell Alert Service Bulletin No. 429–15–24, Revision A, dated September 23, 2015, which specifies updating the Bell 429 maintenance manual with Revision 24 to incorporate the revised airworthiness limitations for the NLG assembly, NLG main fitting to bellcrank bolt, and the NLG main fitting. E:\FR\FM\19FER1.SGM 19FER1

Agencies

[Federal Register Volume 84, Number 33 (Tuesday, February 19, 2019)]
[Rules and Regulations]
[Pages 4684-4685]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2019-02593]


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NUCLEAR REGULATORY COMMISSION

10 CFR Part 72

[NRC-2018-0221]
RIN 3150-AK18


List of Approved Spent Fuel Storage Casks: Holtec International 
HI-STORM 100 Multipurpose Canister Cask System, Certificate of 
Compliance No. 1014, Amendment Nos. 11 and 12

AGENCY: Nuclear Regulatory Commission.

ACTION: Direct final rule; confirmation of effective date.

-----------------------------------------------------------------------

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is confirming the 
effective date of February 25, 2019, for the direct final rule that was 
published in the Federal Register on December 12, 2018. This direct 
final rule amended the NRC's spent fuel storage regulations by revising 
the Holtec International HI-STORM 100 Multipurpose Canister Cask System 
(HI-STORM 100 System) listing within the ``List of approved spent fuel 
storage casks'' to include Amendment Nos. 11 and 12 to Certificate of 
Compliance No. 1014. Amendment Nos. 11 and 12 revise multiple items in 
the technical specifications for multi-purpose canister models listed 
under Certificate of Compliance No. 1014; most of these revisions 
involve changes to the authorized contents. In addition, Amendment No. 
11 makes several other editorial changes.

DATES: The effective date of February 25, 2019, for the direct final 
rule published December 12, 2018 (83 FR 63794), is confirmed.

ADDRESSES: Please refer to Docket ID NRC-2018-0221 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 https://www.regulations.gov and search for Docket ID NRC-2018-0221. Address 
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: Carol.Gallagher@nrc.gov. 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 https://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 pdr.resource@nrc.gov. The proposed amendments to the 
certificate, the proposed changes to the technical specifications, and 
the preliminary safety evaluation reports are available in ADAMS for 
Amendment No. 11 under Accession No. ML18141A560 and Amendment No. 12 
under Accession No. ML18087A055. The final amendments to the 
certificate, final changes to the technical specifications, and final 
safety evaluation reports can also be viewed in ADAMS under Accession 
No. ML18355A369.
     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: Yen-Ju Chen, Office of Nuclear 
Material Safety and Safeguards; telephone: 301-415-1018; email: Yen-Ju.Chen@nrc.gov or Vanessa Cox, Office of Nuclear Material Safety and 
Safeguards; telephone: 301-415-8342; email: Vanessa.Cox@nrc.gov. Both 
are staff of the U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001.

SUPPLEMENTARY INFORMATION: On December 12, 2018 (83 FR 63794), the NRC 
published a direct final rule amending its regulations in part 72 of 
title 10 of the Code of Federal Regulations (10 CFR) to the HI-STORM 
100 System listing within the ``List of approved spent fuel storage 
casks'' to include Amendment Nos. 11 and 12 to Certificate of 
Compliance No. 1014. Amendment Nos. 11 and 12 revise multiple items in 
the technical specifications for multi-purpose canister models listed 
under Certificate of Compliance No. 1014; most of these revisions 
involve changes to the authorized contents. In addition, Amendment No. 
11 makes several other editorial changes.
    In the direct final rule, the NRC stated that if no significant 
adverse comments were received, the direct final rule would become 
effective on February 25, 2019. As described more fully in the direct 
final rule, 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.
    The NRC received two comments and has determined that they are not 
significant adverse comments. One comment questioned the short-term 
economic gains. As this rulemaking only addressed changes to the 
technical specifications for dry shielded canisters used to store 
nuclear waste on-site, the NRC determined this comment to be out of 
scope of this direct final rule. The second comment concerned specific 
casks used at a reactor site, a direct final rule for another storage 
cask, and another cask that is the subject of an NRC enforcement 
action. These issues are also outside the scope of this direct final 
rule.
    The second commenter also stated that the environmental assessment 
for this direct final rule did not consider the effects of certain 
natural phenomena. Pursuant to 10 CFR part 72, the NRC requires that an 
applicant for a spent fuel storage system provide the design bases, 
design criteria, and the margins of safety for the system in its safety 
analysis. The design bases, design criteria, and safety margins include 
consideration of applicable natural phenomena. In its review, the NRC 
determined that the cask system is designed to mitigate the effects of 
design basis accidents, including human-induced and the most severe 
natural phenomena. Specifically, in considering design requirements for 
each accident condition, the NRC evaluates whether the design would 
prevent loss of confinement, shielding, and criticality control in the 
event of an accident. The NRC identified a broad range of natural

[[Page 4685]]

hazards and accidents that were considered in the environmental 
assessment for this direct final rule. Further, the safety evaluation 
report for the Holtec International HI-STORM 100 Cask System (ADAMS 
Accession No. ML003711865; May 4, 2000) identified all accident-level 
events and conditions, which are Design Events III and IV as defined in 
American National Standard Institute/American Nuclear Society 57.9-
1984. These include natural phenomena and human-induced low-probability 
events such as those listed in Comment 2. The NRC determined in the May 
4, 2000, safety evaluation report that all potential safety 
consequences were considered.
    This direct final rule makes changes to the technical 
specifications of Certificate of Compliance No. 1014 for the HI-STORM 
100 Cask System. However, this direct final rule makes limited and 
routine changes; it does not involve significant changes to the design 
or the fabrication of the cask system. The second comment does not 
raise specific safety concerns regarding the changes made in this 
direct final rule. The second comment did not propose a specific change 
or an addition that could be incorporated into this direct final rule 
and did not raise a relevant issue not previously addressed by the NRC. 
Accordingly, the second comment does not meet the criteria of a 
significant adverse comment. Because no significant adverse comments 
were received, this direct final rule will become effective as 
scheduled.

    Dated at Rockville, Maryland, this 12th day of February 2019.

    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. 2019-02593 Filed 2-15-19; 8:45 am]
BILLING CODE 7590-01-P
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