Guidance for Developing Principal Design Criteria for Non-Light Water Reactors, 9246-9247 [2017-02298]

Download as PDF 9246 Federal Register / Vol. 82, No. 22 / Friday, February 3, 2017 / Notices viewed as involving either safeguards, materials control, or managerial matters. Therefore, pursuant to § 51.22(b) and (c)(25), no environmental impact statement or environmental assessment need be prepared in connection with the approval of this exemption request. IV. Conclusions Accordingly, the Commission has determined that, pursuant to 10 CFR 73.5, the exemption is authorized by law and will not endanger life or property or the common defense and security, and is otherwise in the public interest. Therefore, the Commission hereby grants the licensee’s request for an exemption from the requirements of 10 CFR 73.55(p)(1)(i) and (ii), to authorize that the suspension of security measures must be approved as a minimum by either a licensed senior operator or a certified fuel handler, at a nuclear power plant reactor facility for which the certifications required under 10 CFR 50.82(a)(1) have been submitted. The exemption is effective upon receipt. V. Availability of Documents The documents identified in the following table are available to interested persons. Title Date Exelon letter to NRC, ‘‘Permanent Cessation of Operations at Oyster Creek Nuclear Generating Station.’’ .. Exelon letter to NRC, Clinton Power Station, Unit 1, ‘‘Certification of Permanent Cessation of Power Operations.’’ ........................................................................................................................................................... Exelon letter to NRC, Quad Cities Nuclear Power Station, Units 1 and 2, ‘‘Certification of Permanent Cessation of Power Operations.’’ ......................................................................................................................... NRC letter to Exelon, Oyster Creek Nuclear Generating Station; ‘‘Clinton Power Station, Unit No. 1; and Quad Cities Nuclear Power Station, Units 1 and 2—Approval of Certified Fuel Handler Training and Retraining Program.’’ .......................................................................................................................................... Exelon letter to NRC, Clinton Power Station, Unit No. 1, Quad Cities Nuclear Power Station, Units 1 and 2, and Oyster Creek Nuclear Generating Station, ‘‘Request for Exemption from Specific Provisions in 10 CFR 7355(p)(1)(i) and (p)(1)(ii) Related to the Suspension of Security Measures in an Emergency or During Severe Weather.’’ ............................................................................................................................... Exelon letter to NRC, Oyster Creek Nuclear Generating Station, ‘‘License Amendment Request—Proposed Changes to Technical Specifications Section 6.0 Administrative Controls for Permanently Defueled Condition’’ ............................................................................................................................................................. Exelon letter to NRC, Clinton Power Station, Unit No. 1, ‘‘License Amendment Request—Proposed Changes to Technical Specifications Section 5.0 Administrative Controls for Permanently Defueled Condition’’ ............................................................................................................................................................. Exelon letter to NRC, Quad Cities Nuclear Power Station, Units 1 and 2, ‘‘License Amendment Request— Proposed Changes to Technical Specifications Section 5.0 Administrative Controls for Permanently Defueled Condition ......................................................................................................................................... Exelon Letter to NRC, Quad Cities Nuclear Power Station, Units 1 and 2, ‘‘Withdrawal of Certification of Permanent Cessation of Power Operations.’’ ................................................................................................ Exelon Letter to NRC, Clinton Power Station, Unit No. 1, ‘‘Withdrawal of Certification of Permanent Cessation of Power Operations.’’ ......................................................................................................................... Dated at Rockville, Maryland, this 23rd day of January 2017. For the Nuclear Regulatory Commission. Anne T. Boland, Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2017–02336 Filed 2–2–17; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [NRC–2017–0016] Guidance for Developing Principal Design Criteria for Non-Light Water Reactors Nuclear Regulatory Commission. ACTION: Draft regulatory guide; request for comment. asabaliauskas on DSK3SPTVN1PROD with NOTICES The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG), DG–1330, ‘‘Guidance for Developing Principal Design Criteria for Non-Light VerDate Sep<11>2014 17:26 Feb 02, 2017 Jkt 241001 Submit comments by April 4, 2017. 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. Although a time limit is given, comments and suggestions in connection with items for inclusion in guides currently being developed or improvements in all published guides are encouraged at any time. DATES: AGENCY: SUMMARY: Water Reactors.’’ This DG is a proposed new regulatory guide (RG) to provide designers, applicants, and licensees of non-light water cooled nuclear reactors (non-LWR) guidance for developing principal design criteria (PDC) for a proposed facility. The PDC establish the necessary design, fabrication, construction, testing, and performance requirements for structures, systems, and components important to safety; that is, structures, systems, and components that provide reasonable assurance that the facility can be operated without undue risk to the health and safety of the public. PO 00000 Frm 00056 Fmt 4703 Sfmt 4703 ADAMS accession No. 1/07/2011 ML110070507 6/20/2016 ML16172A137 6/20/2016 ML16172A151 9/06/2016 ML16222A787 8/16/2016 ML16229A133 5/17/2016 ML16138A129 7/28/2016 ML16210A300 10/20/2016 ML16294A203 12/14/2016 ML16349A311 12/14/2016 ML16349A314 You may submit comments by any of the following methods: • Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC–2017–0016. 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. • Mail comments to: Cindy Bladey, Office of Administration, Mail Stop: OWFN–12–H08, 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: Jan Mazza, Office of New Reactors, telephone: 301–415–0498, email: Jan.Mazza@nrc.gov, or Mark Orr, Office of Nuclear Regulatory Research, telephone: 301–415–6003, email: ADDRESSES: E:\FR\FM\03FEN1.SGM 03FEN1 Federal Register / Vol. 82, No. 22 / Friday, February 3, 2017 / Notices Mark.Orr@nrc.gov. Both are staff of the 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–2017– 0016 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 Web site: Go to https://www.regulations.gov and search for Docket ID NRC–2017–0016. • 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 ‘‘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 pdr.resource@nrc.gov. • 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. asabaliauskas on DSK3SPTVN1PROD with NOTICES B. Submitting Comments Please include Docket ID NRC–2017– 0016 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. Additional Information The NRC is issuing for public comment a DG in the NRC’s ‘‘Regulatory VerDate Sep<11>2014 17:26 Feb 02, 2017 Jkt 241001 Guide’’ series. This series was developed to describe and make available to the public information regarding methods that are acceptable to the NRC staff for implementing specific parts of the NRC’s regulations, techniques that the staff uses in evaluating specific issues or postulated events, and data that the staff needs in its review of applications for permits and licenses. The DG, entitled ‘‘Guidance for Developing Principal Design Criteria for Non-Light Water Reactors,’’ is a proposed new RG. The proposed new RG is temporarily identified by its task number, DG–1330. The proposed new RG describes the NRC’s proposed guidance on how the general design criteria (GDC) in Appendix A, ‘‘General Design Criteria for Nuclear Power Plants,’’ of title 10 of the Code of Federal Regulations, part 50, ‘‘Domestic Licensing of Production and Utilization Facilities’’ (10 CFR part 50) apply to non-LWR designs. This guidance may be used by non-LWR reactor designers, applicants, and licensees to develop PDC for non-LWR designs, as required by 10 CFR part 50 for an application for a construction permit, and 10 CFR part 52 for an application for a design certification, combined license, standard design approval, or manufacturing license. The DG also describes the NRC’s proposed guidance for modifying and supplementing the GDC to develop PDC that address two specific non-LWR design concepts: sodium-cooled fast reactors (SFRs), and modular high temperature gas-cooled reactors (mHTGRs). The advanced reactor design criteria (ARDC) are intended to be technologyneutral and, therefore, could apply to any type of non-LWR design. In July 2013, the NRC and U.S. Department of Energy (DOE) established a joint initiative to review and address the existing GDC, which may not directly apply to non-LWR power plant designs. During the review it was determined that the safety objective for some of the current GDC were not applicable to SFR and mHTGR technologies, so entirely new design criteria were developed to address their unique design features. III. Backfitting and Issue Finality The purpose of DG–1330 is to provide regulatory guidance to assist future applicants in developing PDC for nonLWR designs. The NRC approves the PDC, which form part of the licensing basis for the facility. The DG, if finalized, would not constitute regulatory requirements. For this reason, issuance of DG–1330, if finalized, would not constitute backfitting under 10 CFR PO 00000 Frm 00057 Fmt 4703 Sfmt 4703 9247 50.109 (the ‘‘Backfit Rule’’). Future applicants may choose to follow the guidance or utilize another approach in developing principle design criteria for their facilities. Applicants and potential applicants are not, with certain exceptions, protected by either the Backfit Rule or any issue finality provisions under 10 CFR part 52. Neither the Backfit Rule nor the issue finality provisions under 10 CFR part 52—with certain exclusions discussed below—were intended to apply to every NRC action which substantially changes the expectations of current and future applicants. Therefore, the positions in any regulatory guide, if imposed on applicants under 10 CFR 50.34(a)(3), 52.47(a)(3), 52.79(a)(4), 52.137(a)(3), or 52.157(a), would not represent backfitting or a violation of issue finality (except as discussed below). The exceptions to the general principle are applicable whenever a combined license applicant references a 10 CFR part 52 license (i.e., an early site permit or a manufacturing license) and/ or 10 CFR part 52 regulatory approval (i.e., a design certification rule or design approval). There are no current nonLWR applicants or holders of licenses or design certifications for non-LWR designs. Therefore, issuance of DG–1330 in final form would not constitute a violation of issue finality. Dated at Rockville, Maryland, this 31st day of January, 2017. For the Nuclear Regulatory Commission. Edward O’Donnell, Acting Chief, Regulatory Guidance and Generic Issues Branch, Division of Engineering, Office of Nuclear Regulatory Research. [FR Doc. 2017–02298 Filed 2–2–17; 8:45 am] BILLING CODE 7590–01–P POSTAL REGULATORY COMMISSION [Docket Nos. MC2017–82 and CP2017–111] New Postal Products Postal Regulatory Commission. Notice. AGENCY: ACTION: The Commission is noticing recent Postal Service filings for the Commission’s consideration concerning negotiated service agreements. This notice informs the public of the filing, invites public comment, and takes other administrative steps. DATES: Comments are due: February 7, 2017. ADDRESSES: Submit comments electronically via the Commission’s Filing Online system at https:// www.prc.gov. Those who cannot submit SUMMARY: E:\FR\FM\03FEN1.SGM 03FEN1

Agencies

NUCLEAR REGULATORY COMMISSION

[Federal Register Volume 82, Number 22 (Friday, February 3, 2017)]
[Notices]
[Pages 9246-9247]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2017-02298]

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NUCLEAR REGULATORY COMMISSION

[NRC-2017-0016]

Guidance for Developing Principal Design Criteria for Non-Light
Water Reactors

AGENCY: Nuclear Regulatory Commission.

ACTION: Draft regulatory guide; request for comment.

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

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing for
public comment draft regulatory guide (DG), DG-1330, ``Guidance for
Developing Principal Design Criteria for Non-Light Water Reactors.''
This DG is a proposed new regulatory guide (RG) to provide designers,
applicants, and licensees of non-light water cooled nuclear reactors
(non-LWR) guidance for developing principal design criteria (PDC) for a
proposed facility. The PDC establish the necessary design, fabrication,
construction, testing, and performance requirements for structures,
systems, and components important to safety; that is, structures,
systems, and components that provide reasonable assurance that the
facility can be operated without undue risk to the health and safety of
the public.

DATES: Submit comments by April 4, 2017. 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. Although a time limit is given, comments and suggestions in
connection with items for inclusion in guides currently being developed
or improvements in all published guides are encouraged at any time.

ADDRESSES: You may submit comments by any of the following methods:
Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC-2017-0016. 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.
Mail comments to: Cindy Bladey, Office of Administration,
Mail Stop: OWFN-12-H08, 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: Jan Mazza, Office of New Reactors,
telephone: 301-415-0498, email: Jan.Mazza@nrc.gov, or Mark Orr, Office
of Nuclear Regulatory Research, telephone: 301-415-6003, email:

[[Page 9247]]

Mark.Orr@nrc.gov. Both are staff of the 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-2017-0016 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 Web site: Go to https://www.regulations.gov and search for Docket ID NRC-2017-0016.
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 ``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 pdr.resource@nrc.gov.
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-2017-0016 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. Additional Information

The NRC is issuing for public comment a DG in the NRC's
``Regulatory Guide'' series. This series was developed to describe and
make available to the public information regarding methods that are
acceptable to the NRC staff for implementing specific parts of the
NRC's regulations, techniques that the staff uses in evaluating
specific issues or postulated events, and data that the staff needs in
its review of applications for permits and licenses.
The DG, entitled ``Guidance for Developing Principal Design
Criteria for Non-Light Water Reactors,'' is a proposed new RG. The
proposed new RG is temporarily identified by its task number, DG-1330.
The proposed new RG describes the NRC's proposed guidance on how the
general design criteria (GDC) in Appendix A, ``General Design Criteria
for Nuclear Power Plants,'' of title 10 of the Code of Federal
Regulations, part 50, ``Domestic Licensing of Production and
Utilization Facilities'' (10 CFR part 50) apply to non-LWR designs.
This guidance may be used by non-LWR reactor designers, applicants, and
licensees to develop PDC for non-LWR designs, as required by 10 CFR
part 50 for an application for a construction permit, and 10 CFR part
52 for an application for a design certification, combined license,
standard design approval, or manufacturing license. The DG also
describes the NRC's proposed guidance for modifying and supplementing
the GDC to develop PDC that address two specific non-LWR design
concepts: sodium-cooled fast reactors (SFRs), and modular high
temperature gas-cooled reactors (mHTGRs).
The advanced reactor design criteria (ARDC) are intended to be
technology-neutral and, therefore, could apply to any type of non-LWR
design. In July 2013, the NRC and U.S. Department of Energy (DOE)
established a joint initiative to review and address the existing GDC,
which may not directly apply to non-LWR power plant designs. During the
review it was determined that the safety objective for some of the
current GDC were not applicable to SFR and mHTGR technologies, so
entirely new design criteria were developed to address their unique
design features.

III. Backfitting and Issue Finality

The purpose of DG-1330 is to provide regulatory guidance to assist
future applicants in developing PDC for non-LWR designs. The NRC
approves the PDC, which form part of the licensing basis for the
facility. The DG, if finalized, would not constitute regulatory
requirements. For this reason, issuance of DG-1330, if finalized, would
not constitute backfitting under 10 CFR 50.109 (the ``Backfit Rule'').
Future applicants may choose to follow the guidance or utilize another
approach in developing principle design criteria for their facilities.
Applicants and potential applicants are not, with certain exceptions,
protected by either the Backfit Rule or any issue finality provisions
under 10 CFR part 52. Neither the Backfit Rule nor the issue finality
provisions under 10 CFR part 52--with certain exclusions discussed
below--were intended to apply to every NRC action which substantially
changes the expectations of current and future applicants. Therefore,
the positions in any regulatory guide, if imposed on applicants under
10 CFR 50.34(a)(3), 52.47(a)(3), 52.79(a)(4), 52.137(a)(3), or
52.157(a), would not represent backfitting or a violation of issue
finality (except as discussed below).
The exceptions to the general principle are applicable whenever a
combined license applicant references a 10 CFR part 52 license (i.e.,
an early site permit or a manufacturing license) and/or 10 CFR part 52
regulatory approval (i.e., a design certification rule or design
approval). There are no current non-LWR applicants or holders of
licenses or design certifications for non-LWR designs. Therefore,
issuance of DG-1330 in final form would not constitute a violation of
issue finality.

Dated at Rockville, Maryland, this 31st day of January, 2017.

For the Nuclear Regulatory Commission.
Edward O'Donnell,
Acting Chief, Regulatory Guidance and Generic Issues Branch, Division
of Engineering, Office of Nuclear Regulatory Research.
[FR Doc. 2017-02298 Filed 2-2-17; 8:45 am]
BILLING CODE 7590-01-P

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