Supplemental Guidance Regarding the Chromium-Coated Zirconium Alloy Fuel Cladding Accident Tolerant Fuel Concept, 57057-57058 [2019-23186]

Download as PDF khammond on DSKJM1Z7X2PROD with NOTICES Federal Register / Vol. 84, No. 206 / Thursday, October 24, 2019 / Notices general public and other Federal agencies to comment on the following extension of a currently approved collection, as required by the Paperwork Reduction Act of 1995. DATES: Written comments should be received on or before December 23, 2019 to be assured consideration. ADDRESSES: Interested persons are invited to submit written comments on the information collection to Mackie Malaka, National Credit Union Administration, 1775 Duke Street, Suite 6018, Alexandria, Virginia 22314; Fax No. 703–519–8579; or email at PRAComments@NCUA.gov. FOR FURTHER INFORMATION CONTACT: Address requests for additional information to Mackie Malaka at the address above or telephone 703–548– 2704. proper execution of the function of the agency, including whether the information will have practical utility; (b) the accuracy of the agency’s estimate of the burden of the collection of information, including the validity of the methodology and assumptions used; (c) ways to enhance the quality, utility, and clarity of the information to be collected; and (d) ways to minimize the burden of the collection of the information on the respondents, including the use of automated collection techniques or other forms of information technology. SUPPLEMENTARY INFORMATION: [FR Doc. 2019–23212 Filed 10–23–19; 8:45 am] OMB Number: 3133–0098. Title: Advertising of Excess Insurance, 12 CFR part 740.3. Form: None. Type of Review: Extension of a currently approved collection. Abstract: Requirements of 12 CFR 740.3, Advertising of excess insurance, prescribes that federally insured credit unions must disclose in advertising the share or savings account insurance provided by a party other than NCUA. This disclosure statement must include the identity of the carrier, the type and amount of such insurance and must avoid any statement or implication that the carrier is affiliated with NCUA or the federal government. The disclosure requirements under § 740.3 are necessary to ensure that share account holders are aware that their accounts are insured by carriers other than the NCUA. Affected Public: Private Sector: Notfor-profit institutions. Estimated No. of Respondents: 291. Estimated No. of Responses per Respondent: 1. Estimated Total Annual Responses: 291. Estimated Burden Hours per Response: 1. Estimated Total Annual Burden Hours: 291. Reason for Change: Adjustments are attributed to current updated data since the last previous submission. Request for Comments: Comments submitted in response to this notice will be summarized and included in the request for Office of Management and Budget approval. All comments will become a matter of public record. The public is invited to submit comments concerning: (a) Whether the collection of information is necessary for the BILLING CODE 7535–01–P VerDate Sep<11>2014 17:34 Oct 23, 2019 Jkt 250001 By Gerard Poliquin, Secretary of the Board, the National Credit Union Administration, on October 21, 2019. Dated: October 21, 2019. Mackie I. Malaka, NCUA PRA Clearance Officer. NATIONAL SCIENCE FOUNDATION Committee Management Renewal The NSF management officials having responsibility for the advisory committee listed below have determined that renewing this committee for another two years is necessary and in the public interest in connection with the performance of duties imposed upon the Director, National Science Foundation (NSF), by 42 U.S.C. 1861 et seq. This determination follows consultation with the Committee Management Secretariat, General Services Administration. Committee STEM Education Advisory Panel, #2624. Effective date for renewal is October 18, 2019. For more information, please contact Crystal Robinson, NSF, at (703) 292–8687. Dated: October 18, 2019. Crystal Robinson, Committee Management Officer. [FR Doc. 2019–23147 Filed 10–23–19; 8:45 am] BILLING CODE 7555–01–P 57057 Draft interim staff guidance; request for comment. ACTION: The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on its draft interim staff guidance which is intended to facilitate the staff’s understanding of the inreactor phenomena important to safety for the chromium-coated zirconium alloy fuel cladding concepts, as well as to provide guidance for NRC staff reviewing vendor applications. Chromium-coated zirconium alloy fuel cladding concepts are being pursued by several U.S. fuel vendors as part of the U.S. Department of Energy’s accident tolerant fuel program. DATES: Submit comments by November 25, 2019. Comments received after this date will be considered if it is practical to do so, but the Commission is able to ensure consideration only for comments received before this date. ADDRESSES: You may submit comments by any of the following methods: • Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC–2019–0208. Address questions about NRC dockets IDs in www.regulations.gov to Jennifer Borges; telephone: 301–287–9127; email: Jennifer.Borges@nrc.gov. For technical questions, contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this document. • Mail comments to: Office of Administration, Mail Stop: TWFN–7– A60M, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001, ATTN: Program Management, Announcements and Editing Staff. 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: Tekia Govan, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001; telephone: 301–415–6197; email: Tekia.Govan@nrc.gov. SUPPLEMENTARY INFORMATION: SUMMARY: I. Obtaining Information and Submitting Comments NUCLEAR REGULATORY COMMISSION [NRC–2019–0208] Supplemental Guidance Regarding the Chromium-Coated Zirconium Alloy Fuel Cladding Accident Tolerant Fuel Concept Nuclear Regulatory Commission. AGENCY: PO 00000 Frm 00059 Fmt 4703 Sfmt 4703 A. Obtaining Information Please refer to Docket ID NRC–2019– 0208 when contacting the NRC about the availability of information for this action. You may obtain publiclyavailable 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–2019–0208. E:\FR\FM\24OCN1.SGM 24OCN1 57058 Federal Register / Vol. 84, No. 206 / Thursday, October 24, 2019 / Notices • 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 Draft Interim Staff Guidance Supplemental Guidance Regarding the Chromium-coated Zirconium Alloy Fuel Cladding Accident Tolerant Fuel Concept is available in ADAMS under Accession No. ML19276G621. • 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. khammond on DSKJM1Z7X2PROD with NOTICES B. Submitting Comments Please include Docket ID NRC–2019– 0208 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 https:// 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. Background This interim staff guidance (ISG) is intended to provide guidance for NRC staff reviewing applications involving fuel products with chromium-coated zirconium alloy cladding. For coated claddings of this type, a phenomena identification and ranking table (PIRT) was generated for the NRC by Pacific Northwest National Laboratory; the guidance provided in this ISG extensively references the PIRT report, ‘‘Degradation and Failure Phenomena of Accident Tolerant Fuel Concepts: Chromium Coated Zirconium Alloy Cladding,’’ issued June 2019. The VerDate Sep<11>2014 17:34 Oct 23, 2019 Jkt 250001 suggested cladding properties specified acceptable fuel design limits and new failure mechanisms sections from the PIRT are replicated in Appendices B and C. These appendices supersede Sections 5.1 and 5.2 of the PIRT report. This ISG is not intended as standalone review guidance, but instead supplements NUREG–0800, ‘‘Standard Review Plan,’’ Section 4.2, ‘‘Fuel System Design,’’ and discusses the potential impact of coated claddings on reviews performed under Standard Review Plan (SRP), Section 4.3, ‘‘Nuclear Design,’’ Section 4.4, ‘‘Thermal and Hydraulic Design,’’ and Chapter 15, ‘‘Transient and Accident Analysis.’’ In addition to the guidance provided in this ISG, reviewers of coated cladding applications should familiarize themselves with the PIRT report and with the relevant sections of the SRP. The PIRT report and this ISG focus primarily on metallic chromium coatings applied to a zirconium alloy base metal, with some additional discussion that is applicable to chromium-based ceramic coatings. Reviewers of submittals on ceramic chromium-coated zirconium alloy claddings should carefully read the PIRT to determine the applicability to the review. This ISG does not apply to reviews of fuel products other than metallic or ceramic chromium-based coatings on a zirconium alloy substrate. Dated at Rockville, Maryland, this 18th day of October, 2019. For the Nuclear Regulatory Commission. Tekia V. Govan, Project Manager, ROP Support and Generic Communication Branch, Division of Inspection and Regional Support, Office of Nuclear Reactor Regulation. [FR Doc. 2019–23186 Filed 10–23–19; 8:45 am] BILLING CODE 7590–01–P NUCLEAR WASTE TECHNICAL REVIEW BOARD Board Meeting The U.S. Nuclear Waste Technical Review Board will meet in Alexandria, Virginia, on November 19, 2019 to review information on DOE research and development activities related to drying, packaging, and dry storage of spent nuclear fuel. Pursuant to its authority under section 5051 of Public Law 100–203, Nuclear Waste Policy Amendments Act (NWPAA) of 1987, the U.S. Nuclear Waste Technical Review Board will hold a public meeting in Alexandria, PO 00000 Frm 00060 Fmt 4703 Sfmt 4703 Virginia, on Tuesday, November 19, 2019, to review information on U.S. Department of Energy (DOE) research and development (R&D) activities related to drying, packaging, and dry storage of spent nuclear fuel (SNF), including aluminum-clad SNF. The Board is an independent federal agency established by Congress to conduct an ongoing technical and scientific evaluation of activities undertaken by DOE to manage and dispose of SNF and high-level radioactive waste (HLW). The Board meeting will be held at the Embassy Suites Alexandria Hotel, 1900 Diagonal Road, Alexandria, VA 22314. The hotel telephone number is (703) 684–5900. The meeting will begin at 8:00 a.m. and is scheduled to adjourn at 5:00 p.m. Speakers representing the DOE Office of Nuclear Energy, the DOE Office of Environmental Management, and the national laboratories will report on R&D projects related to the drying, packaging, and dry storage of SNF. Computer modeling of the thermal behavior of SNF casks and canisters also will be discussed. Information on the development of the DOE standardized canister for DOE-managed SNF and research on long-term dry storage of aluminum-clad SNF will be presented. Additionally, the Board will hear presentations from researchers in other countries, where the drying and drystorage of aluminum-clad SNF is under examination. A detailed meeting agenda will be available on the Board’s website at www.nwtrb.gov approximately one week before the meeting. The meeting will be open to the public, and opportunities for public comment will be provided before the lunch break and again at the end of the meeting. Those wanting to speak are encouraged to sign the Public Comment Register at the check-in table near the entrance to the meeting room. Speakers will be taken in the order in which they signed in and depending on the number a time limit on individual remarks may be set. However, written comments of any length may be submitted to the Board staff or by mail or electronic mail. All comments received in writing will be included in the meeting record, which will be posted on the Board’s website after the meeting. The workshop will be webcast, and the link to the webcast will be available on the Board’s website (www.nwtrb.gov) a few days before the workshop. An archived version of the webcast will be available on the Board’s website following the workshop. The transcript of the workshop will be available on the Board’s website by January 20, 2020. E:\FR\FM\24OCN1.SGM 24OCN1

Agencies

[Federal Register Volume 84, Number 206 (Thursday, October 24, 2019)]
[Notices]
[Pages 57057-57058]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2019-23186]


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NUCLEAR REGULATORY COMMISSION

[NRC-2019-0208]


Supplemental Guidance Regarding the Chromium-Coated Zirconium 
Alloy Fuel Cladding Accident Tolerant Fuel Concept

AGENCY: Nuclear Regulatory Commission.

ACTION: Draft interim staff guidance; request for comment.

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

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is soliciting 
public comment on its draft interim staff guidance which is intended to 
facilitate the staff's understanding of the in-reactor phenomena 
important to safety for the chromium-coated zirconium alloy fuel 
cladding concepts, as well as to provide guidance for NRC staff 
reviewing vendor applications. Chromium-coated zirconium alloy fuel 
cladding concepts are being pursued by several U.S. fuel vendors as 
part of the U.S. Department of Energy's accident tolerant fuel program.

DATES: Submit comments by November 25, 2019. Comments received after 
this date will be considered if it is practical to do so, but the 
Commission is able to ensure consideration only for comments received 
before this date.

ADDRESSES: You may submit comments by any of the following methods:
     Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC-2019-0208. Address 
questions about NRC dockets IDs in www.regulations.gov 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: Office of Administration, Mail Stop: 
TWFN-7-A60M, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001, ATTN: Program Management, Announcements and Editing Staff.
    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: Tekia Govan, Office of Nuclear Reactor 
Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001; telephone: 301-415-6197; email: [email protected].

SUPPLEMENTARY INFORMATION: 

I. Obtaining Information and Submitting Comments

A. Obtaining Information

    Please refer to Docket ID NRC-2019-0208 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-2019-0208.

[[Page 57058]]

     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 [email protected]. The Draft Interim Staff Guidance 
Supplemental Guidance Regarding the Chromium-coated Zirconium Alloy 
Fuel Cladding Accident Tolerant Fuel Concept is available in ADAMS 
under Accession No. ML19276G621.
     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-2019-0208 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 https://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. Background

    This interim staff guidance (ISG) is intended to provide guidance 
for NRC staff reviewing applications involving fuel products with 
chromium-coated zirconium alloy cladding. For coated claddings of this 
type, a phenomena identification and ranking table (PIRT) was generated 
for the NRC by Pacific Northwest National Laboratory; the guidance 
provided in this ISG extensively references the PIRT report, 
``Degradation and Failure Phenomena of Accident Tolerant Fuel Concepts: 
Chromium Coated Zirconium Alloy Cladding,'' issued June 2019. The 
suggested cladding properties specified acceptable fuel design limits 
and new failure mechanisms sections from the PIRT are replicated in 
Appendices B and C. These appendices supersede Sections 5.1 and 5.2 of 
the PIRT report.
    This ISG is not intended as stand-alone review guidance, but 
instead supplements NUREG-0800, ``Standard Review Plan,'' Section 4.2, 
``Fuel System Design,'' and discusses the potential impact of coated 
claddings on reviews performed under Standard Review Plan (SRP), 
Section 4.3, ``Nuclear Design,'' Section 4.4, ``Thermal and Hydraulic 
Design,'' and Chapter 15, ``Transient and Accident Analysis.'' In 
addition to the guidance provided in this ISG, reviewers of coated 
cladding applications should familiarize themselves with the PIRT 
report and with the relevant sections of the SRP.
    The PIRT report and this ISG focus primarily on metallic chromium 
coatings applied to a zirconium alloy base metal, with some additional 
discussion that is applicable to chromium-based ceramic coatings. 
Reviewers of submittals on ceramic chromium-coated zirconium alloy 
claddings should carefully read the PIRT to determine the applicability 
to the review.
    This ISG does not apply to reviews of fuel products other than 
metallic or ceramic chromium-based coatings on a zirconium alloy 
substrate.

    Dated at Rockville, Maryland, this 18th day of October, 2019.

    For the Nuclear Regulatory Commission.

Tekia V. Govan,
Project Manager, ROP Support and Generic Communication Branch, Division 
of Inspection and Regional Support, Office of Nuclear Reactor 
Regulation.
[FR Doc. 2019-23186 Filed 10-23-19; 8:45 am]
 BILLING CODE 7590-01-P
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