[Federal Register Volume 78, Number 61 (Friday, March 29, 2013)]
[Proposed Rules]
[Pages 19148-19149]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2013-06387]
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Proposed Rules
Federal Register
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This section of the FEDERAL REGISTER contains notices to the public of
the proposed issuance of rules and regulations. The purpose of these
notices is to give interested persons an opportunity to participate in
the rule making prior to the adoption of the final rules.
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Federal Register / Vol. 78, No. 61 / Friday, March 29, 2013 /
Proposed Rules
[[Page 19148]]
NUCLEAR REGULATORY COMMISSION
10 CFR Part 72
[NRC-2013-0051]
Shielding and Radiation Protection Review Effort and Licensing
Conditions for Dry Storage Applications
AGENCY: Nuclear Regulatory Commission.
ACTION: Draft interim staff guidance; request for public comment.
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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) requests public
comment on Draft Spent Fuel Storage and Transportation Interim Staff
Guidance No. 26A (SFST-ISG-26A), Revision 0, ``Shielding and Radiation
Protection Review Effort and Licensing Conditions for 10 CFR Part 72
Applications.''
DATES: Submit comments by May 13, 2013. Comments received after this
date will be considered, if it is practical to do so; however, the NRC
staff is only able to ensure consideration of comments received on or
before this date.
ADDRESSES: You may access information and comment submissions related
to this document, which the NRC possesses and is publicly available, by
searching on http://www.regulations.gov under Docket ID NRC-2013-0051.
You may submit comments by any the following methods:
Federal Rulemaking Web Site: Go to http://www.regulations.gov and search for Docket ID NRC-2013-0051. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-492-
3668; email: [email protected].
Mail Comments to: Cindy Bladey, Chief, Rules,
Announcements, and Directives Branch (RADB), Office of Administration,
Mail Stop: TWB-05-B01M, U.S. Nuclear Regulatory Commission, Washington,
DC 20555-0001.
Fax Comments to: RDB at 301-492-3446.
For additional direction on accessing information and submitting
comments, see ``Accessing Information and Submitting Comments'' in the
SUPPLEMENTARY INFORMATION section of this document.
FOR FURTHER INFORMATION CONTACT: Mr. Michel Call, Office of Nuclear
Material Safety and Safeguards, U.S. Nuclear Regulatory Commission,
Washington, DC 20555-0001; telephone: 301-492-3289; email:
[email protected].
SUPPLEMENTARY INFORMATION:
I. Accessing Information and Submitting Comments
A. Accessing Information
Please refer to Docket ID NRC-2013-0051 when contacting the NRC
about the availability of information regarding this document. You may
access information related to this document by any of the following
methods:
Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2013-0051.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may access publicly-available documents online in the NRC
Library at http://www.nrc.gov/reading-rm/adams.html. To begin the
search, select ``ADAMS Public Documents'' and then 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 draft SFST-ISG-26A, Revision 0 is available
electronically under ADAMS Accession No. ML13010A570.
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-2013-0051 in the subject line of your
comment submission, in order to ensure that the NRC is able to make
your comment submission available to the public in this docket.
The NRC cautions you not to include identifying or contact
information that 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 submissions into ADAMS.
II. Further Information
The draft SFST-ISG provides guidance to NRC staff when reviewing
the shielding and radiation protection portions of applications for
certificates of compliance (CoC), specific licenses, and amendments
submitted in accordance with part 72 of Title 10 of the Code of Federal
Regulations (10 CFR), ``Licensing Requirements for the Independent
Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and
Reactor-Related Greater Than Class C Waste,'' (10 CFR part 72) Subpart
L, ``Approval of Spent Fuel Storage Casks,'' and Subpart B, ``License
Application, Form, and Contents.'' The draft SFST-ISG-26A proposes to
revise the shielding and radiation protection review procedures
contained in NUREG-1536, Revision 1, ``Standard Review Plan for Spent
Fuel Dry Storage Systems at a General License Facility,'' and NUREG-
1567, ``Standard Review Plan for Spent Fuel Dry Storage Facilities.''
The draft SFST-ISG revises these review procedures by enhancing their
prioritization; providing guidance regarding conditions the staff
should include in certificates of compliance, specific licenses, and
associated technical specifications; and providing guidance regarding
the analyses that the staff should verify are included by applicants in
applications submitted under 10 CFR Part 72 and the staff's evaluation
of those analyses.
[[Page 19149]]
III. Background
The NRC issues SFST-ISGs to communicate insights and lessons
learned and to address emergent issues not covered in SFST Standard
Review Plans (SRPs). In this way, the NRC staff and stakeholders may
use the guidance in an SFST-ISG document before it is incorporated into
a formal SRP revision.
The NRC has developed draft SFST-ISG-26A, Revision 0 to (1) enhance
the prioritization of shielding and radiation protection review
procedures to improve the effectiveness and efficiency of staff reviews
of these areas; (2) provide guidance regarding the conditions that the
staff should include in certificates of compliance, specific licenses,
and associated technical specifications; and (3) provide guidance
regarding the analyses that the staff should verify are included by
applicants in applications submitted under 10 CFR Part 72 and the
staff's evaluation of those analyses.
Proposed Action
By this action, the NRC is requesting public comments on draft
SFST-ISG-26A. This SFST-ISG proposes certain revisions to NRC guidance
on implementation of the requirements in 10 CFR Part 72. Along with
comments on this draft SFST-ISG, the NRC invites the public to include
suggestions for alternatives to the guidance, or parts thereof,
proposed to address the two issues described in this draft SFST-ISG and
to describe how those suggested alternatives adequately address the
issues. The NRC also invites comments that include information
regarding facility operations and exposures that support the comments
or that the commenter thinks NRC should consider. The NRC will make a
final determination regarding issuance of SFST-ISG-26A after it
considers any public comments received in response to this request.
Backfitting and Issue Finality
This ISG provides guidance to the NRC staff reviewers on: (1)
Establishing the priorities of NRC's shielding and radiation protection
review procedures for applications for initial and amendments of spent
nuclear fuel dry storage system CoCs and applications for specific-
license independent spent fuel storage installation licenses and
license amendments; (2) verifying the inclusion and evaluating the
scope of applicant's analyses of radiation protection and shielding for
these systems and installations; and (3) stating conditions the staff
should include in CoCs, licenses, and technical specifications.
Prioritization of staff review procedures, verification and evaluation
of an applicant's analyses, and the determination of appropriate
conditions to be included in CoCs, licenses, and technical
specifications are not matters to which backfitting or issue finality
protections apply. Staff implementation of such guidance in the context
of applications does not result in backfitting or non-compliance with
issue finality protection provisions. For this reason, the NRC has not
prepared a backfit analysis for this ISG.
For the Nuclear Regulatory Commission.
Dated at Rockville, Maryland, this 13th day of March 2013.
Mark D. Lombard,
Director, Division of Spent Fuel Storage and Transportation, Office of
Nuclear Material Safety and Safeguards.
[FR Doc. 2013-06387 Filed 3-28-13; 8:45 am]
BILLING CODE 7590-01-P