83_FR_39629 83 FR 39475 - Dry Storage and Transportation of High Burnup Spent Nuclear Fuel

83 FR 39475 - Dry Storage and Transportation of High Burnup Spent Nuclear Fuel

NUCLEAR REGULATORY COMMISSION

Federal Register Volume 83, Issue 154 (August 9, 2018)

Page Range39475-39476
FR Document2018-16994

The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft NUREG, NUREG-2224, ``Dry Storage and Transportation of High Burnup Spent Nuclear Fuel.'' The draft NUREG provides technical background information applicable to high burnup spent nuclear fuel (HBU SNF), provides an engineering assessment of recent NRC-sponsored mechanical testing of HBU SNF, and proposes example approaches for licensing and certification of HBU SNF in transportation and dry storage.

Federal Register, Volume 83 Issue 154 (Thursday, August 9, 2018)
[Federal Register Volume 83, Number 154 (Thursday, August 9, 2018)]
[Notices]
[Pages 39475-39476]
From the Federal Register Online  [www.thefederalregister.org]
[FR Doc No: 2018-16994]


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NUCLEAR REGULATORY COMMISSION

[NRC-2018-0066]


Dry Storage and Transportation of High Burnup Spent Nuclear Fuel

AGENCY: Nuclear Regulatory Commission.

ACTION: Draft NUREG; request for comment.

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

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing for 
public comment a draft NUREG, NUREG-2224, ``Dry Storage and 
Transportation of High Burnup Spent Nuclear Fuel.'' The draft NUREG 
provides technical background information applicable to high burnup 
spent nuclear fuel (HBU SNF), provides an engineering assessment of 
recent NRC-sponsored mechanical testing of HBU SNF, and proposes 
example approaches for licensing and certification of HBU SNF in 
transportation and dry storage.

DATES: Submit comments on the draft NUREG-2224 by September 24, 2018. 
Comments received after this date will be considered if it is practical 
to do so, but the NRC is able to ensure consideration only for comments 
received on or before this date.

ADDRESSES: You may submit comments by any of the following methods:
     Federal Rulemaking Website: Go to http://www.regulations.gov and search for Docket ID NRC-2018-0066. Address 
questions about NRC dockets to Jennifer Borges; telephone: 301-287-
9127; email: [email protected]. For technical questions, contact 
the individual listed in the FOR FURTHER INFORMATION CONTACT section of 
this document.
     Mail comments to: May Ma, Office of Administration, Mail 
Stop: TWFN-7-A60M, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001.
    For additional direction on obtaining information and submitting 
comments, see ``Obtaining Information and Submitting Comments'' in the 
SUPPLEMENTARY INFORMATION section of this document.

FOR FURTHER INFORMATION CONTACT: Wendy Reed, Office of Nuclear Material 
Safety and Safeguards, telephone: 301-415-7213; email: 
[email protected]; U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001.

SUPPLEMENTARY INFORMATION:

I. Obtaining Information and Submitting Comments

A. Obtaining Information

    Please refer to Docket ID NRC-2018-0066 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-2018-0066.
     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-

[[Page 39476]]

415-4737, or by email to [email protected]. Draft NUREG-2224, ``Dry 
Storage and Transportation of High Burnup Spent Nuclear Fuel,'' is 
available in ADAMS under Accession No. ML18214A132
     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.

B. Submitting Comments

    Please include Docket ID NRC-2018-0066 in your comment submission.
    The NRC cautions you not to include identifying or contact 
information that you do not want to be publicly disclosed in your 
comment submission. The NRC will post all comment submissions at http://www.regulations.gov as well as enter the comment submissions into 
ADAMS. The NRC does not routinely edit comment submissions to remove 
identifying or contact information.
    If you are requesting or aggregating comments from other persons 
for submission to the NRC, then you should inform those persons not to 
include identifying or contact information that they do not want to be 
publicly disclosed in their comment submission. Your request should 
state that the NRC does not routinely edit comment submissions to 
remove such information before making the comment submissions available 
to the public or entering the comment into ADAMS.

II. Discussion

    Historically, the potential for changes in the cladding performance 
of HBU SNF to compromise the analyzed fuel configuration in 
transportation packages and dry storage systems has been addressed 
through safety review guidance (Interim Staff Guidance (ISG)--11, 
Revision 3, ``Cladding Considerations for the Transportation and 
Storage of Spent Fuel'' (ADAMS Accession No. ML033230335); NUREG-1536, 
Revision 1, ``Standard Review Plan for Spent Fuel Dry Storage Systems 
at a General License Facility'' (ADAMS Accession No. ML101040620)). 
Time-dependent changes on the cladding performance of HBU SNF are 
primarily driven by the fuel's temperature, rod internal pressure (and 
corresponding pressure-induced cladding hoop stresses), and the 
environment during dry storage or transport operations. ISG-11, 
Revision 3 and NUREG-1536, Revision 1 defines adequate fuel conditions, 
including peak cladding temperatures during short-term loading 
operations to prevent and mitigate degradation of the cladding.
    Draft NUREG-2224, ``Dry Storage and Transportation of High Burnup 
Spent Nuclear Fuel,'' (ADAMS Accession No. ML18214A132) is a technical 
basis document which expands on the aspects of ISG-11, Rev. 3 and 
NUREG-1536, Rev. 1 that pertain to hydride reorientation in HBU SNF 
cladding. Hydride reorientation is a process in which the orientation 
of hydrides precipitated in HBU SNF cladding during reactor operation 
changes from the circumferential-axial to the radial-axial direction. 
Draft NUREG-2224 provides an engineering assessment of the results of 
NRC-sponsored research (NUREG/CR-7198, Rev. 1, ``Mechanical Fatigue 
Testing of High-Burnup Fuel for Transportation Application,'' ADAMS 
Accession No. ML17292B057) on the mechanical performance of HBU SNF 
following hydride reorientation; and per the conclusions of that 
assessment, presents example approaches for licensing and certification 
of HBU SNF for transportation (under part 71of title 10 of the Code of 
Federal Regulations (10 CFR), ``Packaging and Transportation of 
Radioactive Material'') and dry storage (under 10 CFR part 72, 
``Licensing Requirements for the Independent Storage of Spent Nuclear 
Fuel and High-Level Radioactive Waste, and Reactor-Related Greater Than 
Class C Waste'').
    The staff will review and consider public comments received on 
draft NUREG-2224 as it finalizes the guidance. The NRC is particularly 
seeking public comment on the following:
    1. Are NRC's assumptions regarding the performance of other 
cladding alloys based on data obtained from HBU SNF with Zircaloy-4 
cladding for evaluating design basis drop accidents reasonable? If not, 
please explain why not.
    2. Are the described licensing and certification approaches easy to 
follow and practical? If not, please explain why not.
    3. Is the proposed approach for evaluation of vibration normally 
incident to transport clear? If not, please explain why not.
    4. Are the discussions on consequence analyses due to hypothetical 
fuel reconfiguration clear and meaningful? If not, please explain why 
not.
    5. Are there any potential conflicts between NUREG-2215, Standard 
Review Plan for Spent Fuel Dry Storage Systems and Facilities, Draft 
for Comment (ADAMS Accession No. ML17310A693) and this document? If so, 
please describe any conflicts.
    6. Is the NRC's reassessment of the ductility transition 
temperature as measured by ring compression testing of defueled HBU SNF 
specimens reasonable? If not, please explain why not.
    In answering the questions, please fully explain your answers. In 
addition, comments are invited on any areas of the draft report.

III. Public Meeting

    The NRC will conduct a public meeting for the purpose of describing 
the draft NUREG and answering questions from the public. The NRC will 
publish a notice of the location, time, and agenda of the meeting on 
the NRC's public meeting website at least 10 calendar days before the 
meeting. Stakeholders should monitor the NRC's public meeting website 
for information about the public meeting at: http://www.nrc.gov/public-involve/public-meetings/index.cfm.

    Dated at Rockville, Maryland, this 3rd day of August 2018.

    For the Nuclear Regulatory Commission.
Michael C. Layton,
Director, Division of Spent Fuel Management, Office of Nuclear Material 
Safety and Safeguards.
[FR Doc. 2018-16994 Filed 8-8-18; 8:45 am]
 BILLING CODE 7590-01-P



                                                                             Federal Register / Vol. 83, No. 154 / Thursday, August 9, 2018 / Notices                                           39475

                                                dated March 16, 2018, the Southern                      complies with the standards and                       an engineering assessment of recent
                                                Nuclear Operating Company (SNC)                         requirements of the Atomic Energy Act                 NRC-sponsored mechanical testing of
                                                requested from the Commission an                        of 1954, as amended (the Act), and the                HBU SNF, and proposes example
                                                exemption to allow departures from Tier                 Commission’s rules and regulations.                   approaches for licensing and
                                                1 information in the certified DCD                      The Commission has made appropriate                   certification of HBU SNF in
                                                incorporated by reference in 10 CFR                     findings as required by the Act and the               transportation and dry storage.
                                                part 52, appendix D, as part of license                 Commission’s rules and regulations in                 DATES: Submit comments on the draft
                                                amendment request 17–042, ‘‘Tier 1 and                  10 CFR chapter I, which are set forth in              NUREG–2224 by September 24, 2018.
                                                Tier 2* Editorial and Consistency                       the license amendment.                                Comments received after this date will
                                                Changes.’’                                                 A notice of consideration of issuance              be considered if it is practical to do so,
                                                   For the reasons set forth in Section 3.2             of amendment to facility operating                    but the NRC is able to ensure
                                                of the NRC staff’s Safety Evaluation that               license or COL, as applicable, proposed               consideration only for comments
                                                which can be found in ADAMS under                       no significant hazards consideration                  received on or before this date.
                                                Accession No. ML18106A638), the                         determination, and opportunity for a
                                                                                                                                                              ADDRESSES: You may submit comments
                                                Commission finds that:                                  hearing in connection with these
                                                                                                                                                              by any of the following methods:
                                                   A. The exemption is authorized by                    actions, was published in the Federal
                                                                                                                                                                 • Federal Rulemaking Website: Go to
                                                law;                                                    Register on March 30, 2018 (83 FR
                                                   B. the exemption presents no undue                                                                         http://www.regulations.gov and search
                                                                                                        13796). No comments were received
                                                risk to public health and safety;                                                                             for Docket ID NRC–2018–0066. Address
                                                                                                        during the 30-day comment period.
                                                   C. the exemption is consistent with                     The Commission has determined that                 questions about NRC dockets to Jennifer
                                                the common defense and security;                        these amendments satisfy the criteria for             Borges; telephone: 301–287–9127;
                                                   D. special circumstances are present                 categorical exclusion in accordance                   email: Jennifer.Borges@nrc.gov. For
                                                in that the application of the rule in this             with 10 CFR 51.22. Therefore, pursuant                technical questions, contact the
                                                circumstance is not necessary to serve                  to 10 CFR 51.22(b), no environmental                  individual listed in the FOR FURTHER
                                                the underlying purpose of the rule;                                                                           INFORMATION CONTACT section of this
                                                                                                        impact statement or environmental
                                                   E. the special circumstances outweigh                assessment need be prepared for these                 document.
                                                any decrease in safety that may result                  amendments.                                              • Mail comments to: May Ma, Office
                                                from the reduction in standardization                                                                         of Administration, Mail Stop: TWFN–7–
                                                caused by the exemption; and                            IV. Conclusion                                        A60M, U.S. Nuclear Regulatory
                                                   F. the exemption will not result in a                   Using the reasons set forth in the                 Commission, Washington, DC 20555–
                                                significant decrease in the level of safety             combined safety evaluation, the staff                 0001.
                                                otherwise provided by the design.                       granted the exemption and issued the                     For additional direction on obtaining
                                                   2. Accordingly, the licensee is granted              amendment that the licensee requested                 information and submitting comments,
                                                an exemption from the certified DCD                     on November 30, 2017.                                 see ‘‘Obtaining Information and
                                                Tier 1 information, with corresponding                     The exemption and amendment were                   Submitting Comments’’ in the
                                                changes to appendix C of the Facility                   issued on May 31, 2018, as part of a                  SUPPLEMENTARY INFORMATION section of
                                                Combined License, as described in the                   combined package to the licensee                      this document.
                                                licensee’s request dated November 30,                   (ADAMS Accession No. ML18106A626).                    FOR FURTHER INFORMATION CONTACT:
                                                2017, as supplemented by the letter                       Dated at Rockville, Maryland, this 3rd day          Wendy Reed, Office of Nuclear Material
                                                dated March 16, 2018. This exemption                    of August 2018.                                       Safety and Safeguards, telephone: 301–
                                                is related to, and necessary for, the                     For the Nuclear Regulatory Commission.              415–7213; email: Wendy.Reed@nrc.gov;
                                                granting of License Amendment No. 125                   Jennifer L. Dixon-Herrity,                            U.S. Nuclear Regulatory Commission,
                                                [for Unit 3 and No. 124 for Unit 4],                    Chief, Licensing Branch 4, Division of                Washington, DC 20555–0001.
                                                which is being issued concurrently with                 Licensing, Siting, and Environmental                  SUPPLEMENTARY INFORMATION:
                                                this exemption.                                         Analysis Office of New Reactors.
                                                   3. As explained in Section 5.0 of the                                                                      I. Obtaining Information and
                                                                                                        [FR Doc. 2018–16995 Filed 8–8–18; 8:45 am]
                                                NRC staff’s Safety Evaluation (ADAMS                                                                          Submitting Comments
                                                                                                        BILLING CODE 7590–01–P
                                                Accession No. ML18106A638), this                                                                              A. Obtaining Information
                                                exemption meets the eligibility criteria
                                                for categorical exclusion set forth in 10                                                                        Please refer to Docket ID NRC–2018–
                                                                                                        NUCLEAR REGULATORY
                                                CFR 51.22(c)(9). Therefore, pursuant to                                                                       0066 when contacting the NRC about
                                                                                                        COMMISSION
                                                10 CFR 51.22(b), no environmental                                                                             the availability of information for this
                                                impact statement or environmental                       [NRC–2018–0066]                                       action. You may obtain publicly-
                                                assessment needs to be prepared in                                                                            available information related to this
                                                                                                        Dry Storage and Transportation of                     action by any of the following methods:
                                                connection with the issuance of the
                                                                                                        High Burnup Spent Nuclear Fuel                           • Federal Rulemaking Website: Go to
                                                exemption.
                                                   4. This exemption is effective as of the             AGENCY: Nuclear Regulatory                            http://www.regulations.gov and search
                                                date of its issuance.                                   Commission.                                           for Docket ID NRC–2018–0066.
                                                                                                        ACTION: Draft NUREG; request for                         • NRC’s Agencywide Documents
                                                III. License Amendment Request                                                                                Access and Management System
                                                                                                        comment.
                                                   By letter dated November 30, 2017                                                                          (ADAMS): You may obtain publicly-
                                                                                                        SUMMARY:   The U.S. Nuclear Regulatory                available documents online in the
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                                                (ADAMS Accession No. ML17334B211),
                                                the licensee requested that the NRC                     Commission (NRC) is issuing for public                ADAMS Public Documents collection at
                                                amend the COLs for VEGP, Units 3 and                    comment a draft NUREG, NUREG–2224,                    http://www.nrc.gov/reading-rm/
                                                4, COLs NPF–91 and NPF–92. The                          ‘‘Dry Storage and Transportation of High              adams.html. To begin the search, select
                                                proposed amendment is described in                      Burnup Spent Nuclear Fuel.’’ The draft                ‘‘Begin Web-based ADAMS Search.’’ For
                                                Section I of this document.                             NUREG provides technical background                   problems with ADAMS, please contact
                                                   The Commission has determined for                    information applicable to high burnup                 the NRC’s Public Document Room (PDR)
                                                these amendments that the application                   spent nuclear fuel (HBU SNF), provides                reference staff at 1–800–397–4209, 301–


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                                                39476                        Federal Register / Vol. 83, No. 154 / Thursday, August 9, 2018 / Notices

                                                415–4737, or by email to pdr.resource@                     Draft NUREG–2224, ‘‘Dry Storage and                measured by ring compression testing of
                                                nrc.gov. Draft NUREG–2224, ‘‘Dry                        Transportation of High Burnup Spent                   defueled HBU SNF specimens
                                                Storage and Transportation of High                      Nuclear Fuel,’’ (ADAMS Accession No.                  reasonable? If not, please explain why
                                                Burnup Spent Nuclear Fuel,’’ is                         ML18214A132) is a technical basis                     not.
                                                available in ADAMS under Accession                      document which expands on the aspects                   In answering the questions, please
                                                No. ML18214A132                                         of ISG–11, Rev. 3 and NUREG–1536,                     fully explain your answers. In addition,
                                                  • NRC’s PDR: You may examine and                      Rev. 1 that pertain to hydride                        comments are invited on any areas of
                                                purchase copies of public documents at                  reorientation in HBU SNF cladding.                    the draft report.
                                                the NRC’s PDR, Room O1–F21, One                         Hydride reorientation is a process in
                                                White Flint North, 11555 Rockville                      which the orientation of hydrides                     III. Public Meeting
                                                Pike, Rockville, Maryland 20852.                        precipitated in HBU SNF cladding                        The NRC will conduct a public
                                                B. Submitting Comments                                  during reactor operation changes from                 meeting for the purpose of describing
                                                                                                        the circumferential-axial to the radial-              the draft NUREG and answering
                                                  Please include Docket ID NRC–2018–                    axial direction. Draft NUREG–2224                     questions from the public. The NRC will
                                                0066 in your comment submission.                        provides an engineering assessment of                 publish a notice of the location, time,
                                                  The NRC cautions you not to include                   the results of NRC-sponsored research                 and agenda of the meeting on the NRC’s
                                                identifying or contact information that                 (NUREG/CR–7198, Rev. 1, ‘‘Mechanical                  public meeting website at least 10
                                                you do not want to be publicly                          Fatigue Testing of High-Burnup Fuel for               calendar days before the meeting.
                                                disclosed in your comment submission.                   Transportation Application,’’ ADAMS                   Stakeholders should monitor the NRC’s
                                                The NRC will post all comment                           Accession No. ML17292B057) on the                     public meeting website for information
                                                submissions at http://                                  mechanical performance of HBU SNF                     about the public meeting at: http://
                                                www.regulations.gov as well as enter the                following hydride reorientation; and per              www.nrc.gov/public-involve/public-
                                                comment submissions into ADAMS.                         the conclusions of that assessment,                   meetings/index.cfm.
                                                The NRC does not routinely edit                         presents example approaches for
                                                comment submissions to remove                                                                                   Dated at Rockville, Maryland, this 3rd day
                                                                                                        licensing and certification of HBU SNF                of August 2018.
                                                identifying or contact information.                     for transportation (under part 71of title
                                                  If you are requesting or aggregating                                                                          For the Nuclear Regulatory Commission.
                                                                                                        10 of the Code of Federal Regulations
                                                comments from other persons for                                                                               Michael C. Layton,
                                                                                                        (10 CFR), ‘‘Packaging and
                                                submission to the NRC, then you should                  Transportation of Radioactive Material’’)             Director, Division of Spent Fuel Management,
                                                inform those persons not to include                                                                           Office of Nuclear Material Safety and
                                                                                                        and dry storage (under 10 CFR part 72,                Safeguards.
                                                identifying or contact information that                 ‘‘Licensing Requirements for the
                                                they do not want to be publicly                         Independent Storage of Spent Nuclear
                                                                                                                                                              [FR Doc. 2018–16994 Filed 8–8–18; 8:45 am]
                                                disclosed in their comment submission.                  Fuel and High-Level Radioactive Waste,                BILLING CODE 7590–01–P
                                                Your request should state that the NRC                  and Reactor-Related Greater Than Class
                                                does not routinely edit comment                         C Waste’’).
                                                submissions to remove such information                     The staff will review and consider                 NUCLEAR REGULATORY
                                                before making the comment                               public comments received on draft                     COMMISSION
                                                submissions available to the public or                  NUREG–2224 as it finalizes the                        [Docket No. 040–08903; NRC–2018–0154]
                                                entering the comment into ADAMS.                        guidance. The NRC is particularly
                                                II. Discussion                                          seeking public comment on the                         Homestake Mining Company of
                                                                                                        following:                                            California; Grants Reclamation Project;
                                                   Historically, the potential for changes                 1. Are NRC’s assumptions regarding                 Groundwater Monitoring Plan
                                                in the cladding performance of HBU                      the performance of other cladding alloys
                                                SNF to compromise the analyzed fuel                     based on data obtained from HBU SNF                   AGENCY:  Nuclear Regulatory
                                                configuration in transportation packages                with Zircaloy-4 cladding for evaluating               Commission.
                                                and dry storage systems has been                        design basis drop accidents reasonable?               ACTION: License amendment application;
                                                addressed through safety review                         If not, please explain why not.                       opportunity to request a hearing and to
                                                guidance (Interim Staff Guidance                           2. Are the described licensing and                 petition for leave to intervene.
                                                (ISG)—11, Revision 3, ‘‘Cladding                        certification approaches easy to follow
                                                Considerations for the Transportation                   and practical? If not, please explain why             SUMMARY:   The U.S. Nuclear Regulatory
                                                and Storage of Spent Fuel’’ (ADAMS                      not.                                                  Commission (NRC) has received an
                                                Accession No. ML033230335); NUREG–                         3. Is the proposed approach for                    application from the Homestake Mining
                                                1536, Revision 1, ‘‘Standard Review                     evaluation of vibration normally                      Company of California (the licensee), for
                                                Plan for Spent Fuel Dry Storage Systems                 incident to transport clear? If not, please           amendment of Materials License No.
                                                at a General License Facility’’ (ADAMS                  explain why not.                                      SUA–1471, which authorizes the
                                                Accession No. ML101040620)). Time-                         4. Are the discussions on                          possession of residual uranium and
                                                dependent changes on the cladding                       consequence analyses due to                           byproduct material in the form of
                                                performance of HBU SNF are primarily                    hypothetical fuel reconfiguration clear               uranium waste tailings and other
                                                driven by the fuel’s temperature, rod                   and meaningful? If not, please explain                byproduct waste generated by the
                                                internal pressure (and corresponding                    why not.                                              licensee’s past milling operations at the
                                                pressure-induced cladding hoop                             5. Are there any potential conflicts               licensee’s uranium mill located in
                                                stresses), and the environment during                                                                         Cibola County, New Mexico. The
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                                                                                                        between NUREG–2215, Standard
                                                dry storage or transport operations. ISG–               Review Plan for Spent Fuel Dry Storage                amendment would update the
                                                11, Revision 3 and NUREG–1536,                          Systems and Facilities, Draft for                     groundwater monitoring plan to adjust
                                                Revision 1 defines adequate fuel                        Comment (ADAMS Accession No.                          the compliance monitoring for the
                                                conditions, including peak cladding                     ML17310A693) and this document? If                    groundwater restoration areas at the
                                                temperatures during short-term loading                  so, please describe any conflicts.                    Grants Reclamation Project site. This
                                                operations to prevent and mitigate                         6. Is the NRC’s reassessment of the                change to the groundwater monitoring
                                                degradation of the cladding.                            ductility transition temperature as                   plan should ensure that coverage is


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Document Created: 2018-08-09 01:10:53
Document Modified: 2018-08-09 01:10:53
CategoryRegulatory Information
CollectionFederal Register
sudoc ClassAE 2.7:
GS 4.107:
AE 2.106:
PublisherOffice of the Federal Register, National Archives and Records Administration
SectionNotices
ActionDraft NUREG; request for comment.
DatesSubmit comments on the draft NUREG-2224 by September 24, 2018. Comments received after this date will be considered if it is practical to do so, but the NRC is able to ensure consideration only for comments received on or before this date.
ContactWendy Reed, Office of Nuclear Material Safety and Safeguards, telephone: 301-415-7213; email: [email protected]; U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.
FR Citation83 FR 39475 

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