Applicability of Existing Regulatory Guides to the Design, Construction, and Operation of an Independent Spent Fuel Storage Installation, 51191 [2019-20972]

Download as PDF Federal Register / Vol. 84, No. 188 / Friday, September 27, 2019 / Notices Additionally, the NRC hosted a public webinar held on August 8, 2019, to obtain comments from individuals in other areas of the country. Specific details regarding the dates, times, locations, and other logistical information for each of the meetings can be found on the NRC’s NEIMA Section 108 public website at https:// www.nrc.gov/waste/decommissioning/ neima-section-108.html. For information about attending the NEIMA Section 108 Category 3 public meetings, please see the public website listed above or contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this document. IV. Local Community Advisory Board Questionnaire The NRC is seeking input from existing CABs in the vicinity of power reactors undergoing decommissioning, similar established stakeholder groups, or local government organizations regarding best practices and lessons learned associated with CABs at decommissioning nuclear power reactors. Comments may be submitted by November 15, 2019. Comments submitted 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 by this date. Dated at Rockville, Maryland, this 24th day of September, 2019. For the Nuclear Regulatory Commission. Bruce A. Watson, Chief, Reactor Decommissioning Branch, Division of Decommissioning, Uranium Recovery, and Waste Programs, Office of Nuclear Material Safety and Safeguards. [FR Doc. 2019–21012 Filed 9–26–19; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [NRC–2019–0157] Applicability of Existing Regulatory Guides to the Design, Construction, and Operation of an Independent Spent Fuel Storage Installation Nuclear Regulatory Commission. ACTION: Regulatory guide; withdrawal. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) is withdrawing Regulatory Guide (RG) 3.53, ‘‘Applicability of Existing Regulatory Guides to the Design, Construction, and Operation of an Independent Spent Fuel Storage Installation.’’ This document is being withdrawn because the information included in the RG has jbell on DSK3GLQ082PROD with NOTICES SUMMARY: VerDate Sep<11>2014 18:29 Sep 26, 2019 Jkt 247001 been superseded by newer guidance and is therefore no longer needed. DATES: The withdrawal of RG 3.53 takes effect on September 27, 2019. ADDRESSES: Please refer to Docket ID NRC–2019–0157 when contacting the NRC about the availability of information regarding this document. You may obtain publicly-available information related to this document, using the following methods: • Federal rulemaking website: Go to https://www.regulations.gov/ and search for Docket ID NRC–2019–0157. Address questions about NRC docket IDs in Regulations.gov to Jennifer Borges; telephone: 301–287–9127; email: Jennifer.Borges@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 Document 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 ADAMS accession number for each document referenced in this notice (if that document is available in ADAMS) is provided the first time that a document is referenced. The basis for the withdrawal of this regulatory guide is found in ADAMS under Accession No. ML19177A369. • 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. Regulatory guides are not copyrighted, and NRC approval is not required to reproduce them. FOR FURTHER INFORMATION CONTACT: Haile Lindsay, Office of Nuclear Material Safety and Safeguards; telephone: 301–415–0616; email: Haile.Lindsay@nrc.gov, or Harriet Karagiannis, Office of Nuclear Regulatory Research; telephone: 301– 415–2493; email: Harriet.Karagiannis@ nrc.gov. Both are staff of the U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001. SUPPLEMENTARY INFORMATION: The NRC is withdrawing RG 3.53 because it has been superseded and is no longer needed. RG 3.53 was published in July 1982 to describe the applicability of existing regulatory guides that would aid in the design, construction, and operation of an independent spent fuel PO 00000 Frm 00085 Fmt 4703 Sfmt 9990 51191 storage installation (ISFSI). At that time, there were no precedents for applications for ISFSIs, there was not a consolidated set of guidance, and information technology did not exist to provide guidance electronically for ISFSIs. The staff issued RG 3.53 to expedite the staff’s reviews of ISFSI applications, which were anticipated under the new requirements in title 10 of the Code of Federal Regulations (10 CFR) part 72, ‘‘Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High Level Radioactive Waste, and Reactor-Related Greater than Class C Waste.’’ Since 1982, many of the guidance documents and regulatory positions listed in the RG have been withdrawn or superseded by more current guidance. Examples of new or revised staff guidance for ISFSIs include RG 3.48, ‘‘Standard Format and Content for the Safety Analysis Report for an Independent Spent Fuel Storage Installation or Monitored Retrievable Storage Installation (Dry Storage),’’ RG 3.50, ‘‘Standard Format and Content for a Specific License Application for An Independent Spent Fuel Storage Installation or Monitored Retrievable Storage Facility,’’ RG 3.60, ‘‘Design of an Independent Spent Fuel Storage Installation (Dry Storage),’’ and RG 3.62, ‘‘Standard Format and Content for the Safety Analysis Report for Onsite Storage of Spent Fuel Storage Casks.’’ These guidance documents incorporate the lessons learned during the licensing process and from operational experiences with ISFSIs. The current information technology available today makes the numerous RGs in the areas of design, construction, and operation of an ISFSI readily available electronically on the NRC’s public website and it is easy for applicants to navigate and identify these guides. Dated at Rockville, Maryland, this 23rd day of September, 2019. For the Nuclear Regulatory Commission. Thomas H. Boyce, Chief, Regulatory Guidance and Generic Issues Branch, Division of Engineering, Office of Nuclear Regulatory Research. [FR Doc. 2019–20972 Filed 9–26–19; 8:45 am] BILLING CODE 7590–01–P E:\FR\FM\27SEN1.SGM 27SEN1

Agencies

[Federal Register Volume 84, Number 188 (Friday, September 27, 2019)]
[Notices]
[Page 51191]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2019-20972]


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

NUCLEAR REGULATORY COMMISSION

[NRC-2019-0157]


Applicability of Existing Regulatory Guides to the Design, 
Construction, and Operation of an Independent Spent Fuel Storage 
Installation

AGENCY: Nuclear Regulatory Commission.

ACTION: Regulatory guide; withdrawal.

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

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is withdrawing 
Regulatory Guide (RG) 3.53, ``Applicability of Existing Regulatory 
Guides to the Design, Construction, and Operation of an Independent 
Spent Fuel Storage Installation.'' This document is being withdrawn 
because the information included in the RG has been superseded by newer 
guidance and is therefore no longer needed.

DATES: The withdrawal of RG 3.53 takes effect on September 27, 2019.

ADDRESSES: Please refer to Docket ID NRC-2019-0157 when contacting the 
NRC about the availability of information regarding this document. You 
may obtain publicly-available information related to this document, 
using the following methods:
     Federal rulemaking website: Go to https://www.regulations.gov/ and search for Docket ID NRC-2019-0157. Address 
questions about NRC docket IDs in Regulations.gov to Jennifer Borges; 
telephone: 301-287-9127; 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 Document 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 ADAMS accession number for each 
document referenced in this notice (if that document is available in 
ADAMS) is provided the first time that a document is referenced. The 
basis for the withdrawal of this regulatory guide is found in ADAMS 
under Accession No. ML19177A369.
     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.
    Regulatory guides are not copyrighted, and NRC approval is not 
required to reproduce them.

FOR FURTHER INFORMATION CONTACT: Haile Lindsay, Office of Nuclear 
Material Safety and Safeguards; telephone: 301-415-0616; email: 
[email protected], or Harriet Karagiannis, Office of Nuclear 
Regulatory Research; telephone: 301-415-2493; email: 
[email protected]. Both are staff of the U.S. Nuclear 
Regulatory Commission, Washington, DC 20555-0001.

SUPPLEMENTARY INFORMATION: The NRC is withdrawing RG 3.53 because it 
has been superseded and is no longer needed. RG 3.53 was published in 
July 1982 to describe the applicability of existing regulatory guides 
that would aid in the design, construction, and operation of an 
independent spent fuel storage installation (ISFSI). At that time, 
there were no precedents for applications for ISFSIs, there was not a 
consolidated set of guidance, and information technology did not exist 
to provide guidance electronically for ISFSIs. The staff issued RG 3.53 
to expedite the staff's reviews of ISFSI applications, which were 
anticipated under the new requirements in title 10 of the Code of 
Federal Regulations (10 CFR) part 72, ``Licensing Requirements for the 
Independent Storage of Spent Nuclear Fuel, High Level Radioactive 
Waste, and Reactor-Related Greater than Class C Waste.''
    Since 1982, many of the guidance documents and regulatory positions 
listed in the RG have been withdrawn or superseded by more current 
guidance. Examples of new or revised staff guidance for ISFSIs include 
RG 3.48, ``Standard Format and Content for the Safety Analysis Report 
for an Independent Spent Fuel Storage Installation or Monitored 
Retrievable Storage Installation (Dry Storage),'' RG 3.50, ``Standard 
Format and Content for a Specific License Application for An 
Independent Spent Fuel Storage Installation or Monitored Retrievable 
Storage Facility,'' RG 3.60, ``Design of an Independent Spent Fuel 
Storage Installation (Dry Storage),'' and RG 3.62, ``Standard Format 
and Content for the Safety Analysis Report for Onsite Storage of Spent 
Fuel Storage Casks.'' These guidance documents incorporate the lessons 
learned during the licensing process and from operational experiences 
with ISFSIs. The current information technology available today makes 
the numerous RGs in the areas of design, construction, and operation of 
an ISFSI readily available electronically on the NRC's public website 
and it is easy for applicants to navigate and identify these guides.

    Dated at Rockville, Maryland, this 23rd day of September, 2019.

    For the Nuclear Regulatory Commission.
Thomas H. Boyce,
Chief, Regulatory Guidance and Generic Issues Branch, Division of 
Engineering, Office of Nuclear Regulatory Research.
[FR Doc. 2019-20972 Filed 9-26-19; 8:45 am]
 BILLING CODE 7590-01-P


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