Interim Staff Guidance: Advanced Reactor Content of Application Project Chapter 10, Control of Occupational Dose, 23054-23056 [2024-07026]
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Federal Register / Vol. 89, No. 65 / Wednesday, April 3, 2024 / Notices
NATIONAL AERONAUTICS AND
SPACE ADMINISTRATION
[Notice: 24–026]
Name of Information Collection:
Survey of the Use of NASA Earth
Observation Data by States, Tribes,
and Territories
National Aeronautics and
Space Administration (NASA).
ACTION: Notice of information collection.
AGENCY:
NASA, as part of its
continuing effort to reduce paperwork
and respondent burden, invites the
general public and other Federal
agencies to take this opportunity to
comment on proposed and/or
continuing information collections, as
required by the Paperwork Reduction
Act of 1995 (PRA).
DATES: Comments are due by June 3,
2024.
ADDRESSES: Written comments and
recommendations for this information
collection should be sent within 60 days
of publication of this notice. You may
send comments, identified by NASA
Notice Number 24–026 to the Federal eRulemaking Portal: https://
www.regulations.gov. Follow the
instructions for sending comments.
FOR FURTHER INFORMATION CONTACT:
Requests for additional information or
copies of the information collection
instrument(s) and instructions should
be directed to NASA PRA Clearance
Officer, Bill Edwards-Bodmer, NASA
Headquarters, 300 E Street SW, JF0000,
Washington, DC 20546, phone 757–864–
7998, or email hq-ocio-pra-program@
mail.nasa.gov.
SUPPLEMENTARY INFORMATION:
SUMMARY:
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I. Abstract
As part of a requirement from the
CHIPS and Science Act of 2022 (sec.
10824, Pub. L. 117–167, 136 Stat. 1742)
the NASA Administrator shall arrange
for the conduct of a survey of the use
of NASA Earth observation data by
States, Tribal organizations, and
territories. The collection of this
information will enable the agency to
understand how Earth observation data
is used, how it might impact decision
making, and where any gaps might
exist.
II. Methods of Collection
Electronic, virtual focus groups, and
in-person focus groups.
III. Data
Title: Survey of the Use of NASA
Earth Observation Data by States,
Tribes, and Territories.
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OMB Number: 2700-new.
Type of review: New collection.
Affected Public: Officials representing
states, tribes, and territories.
Estimated Annual Number of
Activities: 2.
Estimated Number of Respondents
per Activity: 1.
Annual Responses: 2,000.
Estimated Time per Response: 1.25
hours (focus group + quantitative
survey).
Estimated Total Annual Burden
Hours: 2,500.
IV. Request for Comments
Comments are invited on: (1) Whether
the proposed collection of information
is necessary for the proper performance
of the functions of NASA, including
whether the information collected has
practical utility; (2) the accuracy of
NASA’s estimate of the burden
(including hours and cost) of the
proposed collection of information; (3)
ways to enhance the quality, utility, and
clarity of the information to be
collected; and (4) ways to minimize the
burden of the collection of information
on respondents, including automated
collection techniques or the use of other
forms of information technology.
Comments submitted in response to
this notice will be summarized and
included in the request for OMB
approval of this information collection.
They will also become a matter of
public record.
William Edwards-Bodmer,
PRA Clearance Officer, National Aeronautics
and Space Administration.
[FR Doc. 2024–07058 Filed 4–2–24; 8:45 am]
BILLING CODE 7510–13–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2022–0077]
Interim Staff Guidance: Advanced
Reactor Content of Application Project
Chapter 10, Control of Occupational
Dose
Nuclear Regulatory
Commission.
ACTION: Final guidance; issuance.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) issuing Interim Staff
Guidance (ISG) DANU–ISG–2022–04,
Chapter 10, ‘‘Control of Occupational
Dose.’’ The purpose of this ISG is to
provide guidance for prospective
applicants in preparing applications for
non-light water reactor (non-LWR)
designs that use the Licensing
Modernization Project (LMP) process
SUMMARY:
PO 00000
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and to assist the NRC staff in
determining whether such applications
meet the minimum requirements for
construction permits, operating licenses,
combined licenses, manufacturing
licenses, standard design approval, or
design certifications.
DATES: This guidance is effective on
April 3, 2024.
ADDRESSES: Please refer to Docket ID
NRC–2022–0077 when contacting the
NRC about the availability of
information regarding this document.
You may obtain publicly available
information related to this document
using any of the following methods:
• Federal Rulemaking Website: Go to
https://www.regulations.gov and search
for Docket ID NRC–2022–0077. Address
questions about Docket IDs in
Regulations.gov to Stacy Schumann;
telephone: 301–415–0624; email:
Stacy.Schumann@nrc.gov. For technical
questions, contact the individual 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 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, at
301–415–4737, or by email to
PDR.Resource@nrc.gov. The ISG,
DANU–ISG–2022–04, Chapter 10,
‘‘Control of Occupational Dose,’’ is
available in ADAMS under Accession
No. ML23277A142.
• NRC’s PDR: The PDR, where you
may examine and order copies of
publicly available documents, is open
by appointment. To make an
appointment to visit the PDR, please
send an email to PDR.Resource@nrc.gov
or call 1–800–397–4209 or 301–415–
4737, between 8 a.m. and 4 p.m. eastern
time (ET), Monday through Friday,
except Federal holidays.
FOR FURTHER INFORMATION CONTACT:
James O’Driscoll, Office of Nuclear
Reactor Regulation, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001, telephone: 301–415–
1325; email: James.O’Driscoll@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Background
The NRC staff anticipates the
submission of advanced power-reactor
applications within the next few years
based on preapplication engagement
initiated by several prospective
applicants. Because many of these
E:\FR\FM\03APN1.SGM
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Federal Register / Vol. 89, No. 65 / Wednesday, April 3, 2024 / Notices
designs are non-LWRs, the NRC staff
developed technology-inclusive, riskinformed, performance-based guidance
to support the development and review
of these non-LWR applications. The
guidance will facilitate the development
and review of non-LWR applications for
construction permits or operating
licenses under part 50 of title 10 of the
Code of Federal Regulations (10 CFR),
‘‘Domestic Licensing of Production and
Utilization Facilities,’’ or combined
licenses, manufacturing licenses,
standard design approval, or design
certifications under 10 CFR part 52,
‘‘Licenses, Certifications, and Approvals
for Nuclear Power Plants.’’ The NRC
staff notes it is developing a rule to
amend 10 CFR parts 50 and 52 to align
reactor licensing processes and
incorporate lessons learned from new
reactor licensing into the regulations
(RIN 3150–Al66). This ISG may need to
be updated to conform to changes to 10
CFR parts 50 and 52, if any, adopted
through that rulemaking. Further, as of
the date of this final ISG, the NRC staff
is developing an optional performancebased, technology-inclusive regulatory
framework for licensing nuclear power
plants designated as 10 CFR part 53
(RIN 3150–AK31). The NRC intends to
revise this guidance as a part of the
ongoing rulemaking for 10 CFR part 53.
To standardize the development of
content of a non-LWR application, the
NRC staff focused on two activities: the
Advanced Reactor Content of
Application Project (ARCAP) and the
Technology-Inclusive Content of
Application Project (TICAP). The
ARCAP is an NRC-led activity that is
intended to result in guidance for a
complete non-LWR application for
review under 10 CFR part 50 or 10 CFR
part 52, and which the NRC staff would
update, as appropriate, pending the
issuance of the 10 CFR part 50 and 10
CFR part 52 rulemaking as previously
mentioned in this notice, or if the
Commission issues a final 10 CFR part
53 rule. As a result, the ARCAP is broad
and encompasses several industry-led
and NRC-led guidance document
development activities aimed at
facilitating a consistent approach to the
development of application documents.
The TICAP is an industry-led activity
that is focused on providing guidance
on the appropriate scope and depth of
information related to the specific
portions of the safety analysis report
that describe the fundamental safety
functions of the design and document
the safety analysis of the facility using
the LMP-based approach. The LMPbased approach is described in
Regulatory Guide (RG) 1.233, ‘‘Guidance
for a Technology-Inclusive, RiskInformed, and Performance-Based
Methodology to Inform the Licensing
Basis and Content of Applications for
Licenses, Certifications, and Approvals
for Non-Light-Water Reactors,’’
(ADAMS Accession No. ML20091L698).
The ARCAP ISG titled ‘‘Review of
Risk-Informed, Technology-Inclusive
Advanced Reactor Applications—
Roadmap’’ (ARCAP Roadmap ISG) was
developed to provide a general overview
of the information that should be
included in a non-LWR application. The
ARCAP Roadmap ISG also provides a
review roadmap for the NRC staff with
the principal purpose of ensuring
consistency, quality, and uniformity of
NRC staff reviews. The ARCAP
Roadmap ISG includes references to
eight other ARCAP ISGs and a TICAP
RG that are the subject of separate
Federal Register notices (FRNs)
notifying the public of the issuance of
these guidance documents. Information
regarding the eight other ARCAP ISGs
and the TICAP RG can be found in the
table at the end of the ‘‘Discussion’’
section.
II. Discussion
The ARCAP ISG titled, Chapter 10,
‘‘Control of Occupational Dose,’’ that is
the subject of this FRN, was developed
because the current application and
review guidance related to control of
occupational doses is directly
applicable only to light water reactors
and may not fully (or efficiently)
identify the information to be included
in a technology-inclusive, riskinformed, and performance-based
application or provide a review
approach for such an application.
The table in this notice provides the
document description, ADAMS
accession number, and, if appropriate,
the docket identification number.
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Document description
Interim Staff Guidance DANU–ISG–2022–01, ‘‘Advanced Reactor Content of Application Project, ‘Review of
Risk-Informed, Technology-Inclusive Advanced Reactor Applications—Roadmap.’ ’’ ....................................
Interim Staff Guidance DANU–ISG–2022–02, ‘‘Advanced Reactor Content of Application Project Chapter 2,
‘Site Information.’ ’’ ...........................................................................................................................................
Interim Staff Guidance DANU–ISG–2022–03, ‘‘Advanced Reactor Content of Application Project Chapter 9,
‘Control of Routine Plant Radioactive Effluents, Plant Contamination and Solid Waste.’ ’’ ............................
Interim Staff Guidance DANU–ISG–2022–04, ‘‘Advanced Reactor Content of Application Project Chapter 10,
‘Control of Occupational Dose.’ ’’ .....................................................................................................................
Interim Staff Guidance DANU–ISG–2022–05, ‘‘Advanced Reactor Content of Application Project Chapter 11,
‘Organization and Human-System Considerations.’ ’’ ......................................................................................
Interim Staff Guidance DANU–ISG–2022–06, ‘‘Advanced Reactor Content of Application Project Chapter 12,
‘Post-manufacturing and construction Inspection, Testing, and Analysis Program.’ ’’ ....................................
Interim Staff Guidance DANU–ISG–2022–07, ‘‘Advanced Reactor Content of Application Project, ‘Risk-Informed Inservice Inspection/Inservice Testing Programs for Non-LWRs.’ ’’ ....................................................
Interim Staff Guidance DANU–ISG–2022–08, ‘‘Advanced Reactor Content of Application Project, ‘Risk-Informed Technical Specifications.’ ’’ ..................................................................................................................
Interim Staff Guidance DANU–ISG–2022–09, ‘‘Advanced Reactor Content of Application Project, ‘Risk-Informed Performance-Based Fire Protection Program (for Operations).’ ’’ .......................................................
RG 1.253, Revision 0, ‘‘Guidance for a Technology-Inclusive Content of Application Methodology to Inform
the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-LightWater Reactors.’’ ..............................................................................................................................................
Regulatory Analysis for ARCAP ISGs .................................................................................................................
Review of Advanced Reactor Content of Application Project/Technology-Inclusive Content of Application
Project Guidance ..............................................................................................................................................
Response to the Advisory Committee on Reactor Safeguards Letter, ‘‘Review of Advanced Reactor Content
of Application Project/Technology-Inclusive Content of Application Project Guidance’’ .................................
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ADAMS
accession No.
Regulations.gov
docket ID No.
ML23277A139
NRC–2022–0074
ML23277A140
NRC–2022–0075
ML23277A141
NRC–2022–0076
ML23277A142
NRC–2022–0077
ML23277A143
NRC–2022–0078
ML23277A144
NRC–2022–0079
ML23277A145
NRC–2022–0080
ML23277A146
NRC–2022–0081
ML23277A147
NRC–2022–0082
ML23269A222
ML23093A099
NRC–2022–0073
NRC–2022–0074
ML23348A182
NRC–2022–0074
ML24024A025
NRC–2022–0074
03APN1
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Federal Register / Vol. 89, No. 65 / Wednesday, April 3, 2024 / Notices
III. Additional Information
During the 711th meeting of the
Advisory Committee on Reactor
Safeguards (ACRS), December 6–7,
2023, the ACRS, the NRC staff, and
representatives of other stakeholders
discussed guidance documents related
to the ARCAP and the TICAP. On
December 20, 2023, the ACRS issued a
report documenting its review of these
guidance documents (ADAMS
Accession No. ML23348A182). The
conclusions and recommendations in
the ACRS report apply to all the ARCAP
and TICAP guidance documents. In its
December 2023 report, the ACRS did
not recommend any specific changes to
DANU–ISG–2022–04.
Draft DANU–ISG–2022–04, Chapter
10, ‘‘Control of Occupational Dose,’’ was
published in the Federal Register for
public comment on May 25, 2023, (88
FR 33936) with a 45-day comment
period. Subsequently, the comment
period was extended by 30 days as
noted in the Federal Register dated June
28, 2023 (88 FR 41985). The NRC staff
received two public comments from
stakeholders. The NRC staff’s evaluation
and resolution of the public comments
can be found in a document located in
ADAMS under Accession No.
ML23277A151.
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IV. Congressional Review Act
DANU–ISG–2022–04, Chapter 10,
‘‘Control of Occupational Dose,’’ is a
rule as defined in the Congressional
Review Act (5 U.S.C. 801–808).
However, the Office of Management and
Budget has not found it to be a major
rule as defined in the Congressional
Review Act.
V. Backfitting, Forward Fitting, and
Issue Finality
DANU–ISG–2022–04 does not
constitute backfitting as defined in 10
CFR 50.109, ‘‘Backfitting,’’ and as
described in Management Directive
(MD) 8.4, ‘‘Management of Backfitting,
Forward Fitting, Issue Finality, and
Information Requests’’; does not
constitute forward fitting as that term is
defined and described in MD 8.4; and
does not affect the issue finality of any
approval issued under 10 CFR part 52.
The guidance would not apply to any
current licensees or applicants or
existing or requested approvals under
10 CFR part 52, and therefore its
issuance cannot be a backfit or forward
fit or affect issue finality. Further, as
explained in DANU–ISG–2022–04,
applicants and licensees would not be
required to comply with the positions
set forth in DANU–ISG–2022–04.
Dated: March 28, 2024.
VerDate Sep<11>2014
18:18 Apr 02, 2024
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For the Nuclear Regulatory Commission.
Steven T. Lynch,
Chief, Advanced Reactor Policy Branch,
Division of Advanced Reactors and NonPower Production and Utilization Facilities,
Office of Nuclear Reactor Regulation.
[FR Doc. 2024–07026 Filed 4–2–24; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket Nos. 50–263, 50–260, and 50–296;
NRC–2024–0030]
Notice of Intent To Conduct Scoping
Process and Prepare Environmental
Impact Statement; Tennessee Valley
Authority; Browns Ferry Nuclear Plant,
Units 1, 2, and 3
Nuclear Regulatory
Commission.
ACTION: Notice; public scoping meeting
and request for comment.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) will conduct a
scoping process to gather information
necessary to prepare an environmental
impact statement (EIS) to evaluate the
environmental impacts for an
application for the subsequent license
renewal (SLR) of the Renewed Facility
Operating License Nos. DPR–33, DPR–
52, and DPR–68 for Browns Ferry
Nuclear Plant, Units 1, 2, and 3 (Browns
Ferry). The NRC is seeking public
comment on this action and has
scheduled two virtual public scoping
meetings.
SUMMARY:
The NRC will hold two virtual
public scoping meetings on April 11,
2024, at 1 p.m. eastern time (ET) and on
April 18, 2024, at 6 p.m. ET. Details on
both meetings can be found on the
NRC’s Public Meeting Schedule at
https://www.nrc.gov/pmns/mtg. Submit
comments on the scope of the EIS by
May 3, 2024. 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. See Section IV, ‘‘Public Scoping
Meeting,’’ of this notice for additional
information.
DATES:
You may submit comments
by any of the following methods;
however, the NRC encourages electronic
comment submission through the
Federal rulemaking website:
• Federal rulemaking website: Go to
https://regulations.gov and search for
Docket ID NRC–2024–0030. Address
questions about Docket IDs in
Regulations.gov to Stacy Schumann;
telephone: 301–415–0624; email:
ADDRESSES:
PO 00000
Frm 00082
Fmt 4703
Sfmt 4703
Stacy.Schumann@nrc.gov. For technical
questions, contact the individual listed
in the FOR FURTHER INFORMATION
CONTACT section of this document.
• Email comments to:
BrownsFerryEnvironmental@nrc.gov.
• 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:
Jessica Uman˜a, Office of Nuclear
Material Safety and Safeguards, U.S.
Nuclear Regulatory Commission,
Washington, DC 20555–0001; telephone:
301–415–5207, email: Jessica.Umana@
nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Obtaining Information and
Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC–2024–
0030 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://regulations.gov and search for
Docket ID NRC–2024–0030.
• 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, at
301–415–4737, or by email to
PDR.Resource@nrc.gov. The ADAMS
accession number for each document
referenced in this document (if it is
available in ADAMS) is provided the
first time that it is referenced.
• NRC’s PDR: The PDR, where you
may examine and order copies of
publicly available documents, is open
by appointment. To make an
appointment to visit the PDR, please
send an email to PDR.Resource@nrc.gov
or call 1–800–397–4209 or 301–415–
4737, between 8 a.m. and 4 p.m. ET,
Monday through Friday, except Federal
holidays.
• Public Library: A copy of the SLR
application for Browns Ferry, including
E:\FR\FM\03APN1.SGM
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]]>Agencies
[Federal Register Volume 89, Number 65 (Wednesday, April 3, 2024)]
[Notices]
[Pages 23054-23056]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2024-07026]
=======================================================================
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2022-0077]
Interim Staff Guidance: Advanced Reactor Content of Application
Project Chapter 10, Control of Occupational Dose
AGENCY: Nuclear Regulatory Commission.
ACTION: Final guidance; issuance.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) issuing Interim
Staff Guidance (ISG) DANU-ISG-2022-04, Chapter 10, ``Control of
Occupational Dose.'' The purpose of this ISG is to provide guidance for
prospective applicants in preparing applications for non-light water
reactor (non-LWR) designs that use the Licensing Modernization Project
(LMP) process and to assist the NRC staff in determining whether such
applications meet the minimum requirements for construction permits,
operating licenses, combined licenses, manufacturing licenses, standard
design approval, or design certifications.
DATES: This guidance is effective on April 3, 2024.
ADDRESSES: Please refer to Docket ID NRC-2022-0077 when contacting the
NRC about the availability of information regarding this document. You
may obtain publicly available information related to this document
using any of the following methods:
Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC-2022-0077. Address
questions about Docket IDs in Regulations.gov to Stacy Schumann;
telephone: 301-415-0624; email: [email protected]. For technical
questions, contact the individual 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 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, at 301-415-4737,
or by email to [email protected]. The ISG, DANU-ISG-2022-04, Chapter
10, ``Control of Occupational Dose,'' is available in ADAMS under
Accession No. ML23277A142.
NRC's PDR: The PDR, where you may examine and order copies
of publicly available documents, is open by appointment. To make an
appointment to visit the PDR, please send an email to
[email protected] or call 1-800-397-4209 or 301-415-4737, between 8
a.m. and 4 p.m. eastern time (ET), Monday through Friday, except
Federal holidays.
FOR FURTHER INFORMATION CONTACT: James O'Driscoll, Office of Nuclear
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001, telephone: 301-415-1325; email: James.O'[email protected].
SUPPLEMENTARY INFORMATION:
I. Background
The NRC staff anticipates the submission of advanced power-reactor
applications within the next few years based on preapplication
engagement initiated by several prospective applicants. Because many of
these
[[Page 23055]]
designs are non-LWRs, the NRC staff developed technology-inclusive,
risk-informed, performance-based guidance to support the development
and review of these non-LWR applications. The guidance will facilitate
the development and review of non-LWR applications for construction
permits or operating licenses under part 50 of title 10 of the Code of
Federal Regulations (10 CFR), ``Domestic Licensing of Production and
Utilization Facilities,'' or combined licenses, manufacturing licenses,
standard design approval, or design certifications under 10 CFR part
52, ``Licenses, Certifications, and Approvals for Nuclear Power
Plants.'' The NRC staff notes it is developing a rule to amend 10 CFR
parts 50 and 52 to align reactor licensing processes and incorporate
lessons learned from new reactor licensing into the regulations (RIN
3150-Al66). This ISG may need to be updated to conform to changes to 10
CFR parts 50 and 52, if any, adopted through that rulemaking. Further,
as of the date of this final ISG, the NRC staff is developing an
optional performance-based, technology-inclusive regulatory framework
for licensing nuclear power plants designated as 10 CFR part 53 (RIN
3150-AK31). The NRC intends to revise this guidance as a part of the
ongoing rulemaking for 10 CFR part 53.
To standardize the development of content of a non-LWR application,
the NRC staff focused on two activities: the Advanced Reactor Content
of Application Project (ARCAP) and the Technology-Inclusive Content of
Application Project (TICAP). The ARCAP is an NRC-led activity that is
intended to result in guidance for a complete non-LWR application for
review under 10 CFR part 50 or 10 CFR part 52, and which the NRC staff
would update, as appropriate, pending the issuance of the 10 CFR part
50 and 10 CFR part 52 rulemaking as previously mentioned in this
notice, or if the Commission issues a final 10 CFR part 53 rule. As a
result, the ARCAP is broad and encompasses several industry-led and
NRC-led guidance document development activities aimed at facilitating
a consistent approach to the development of application documents.
The TICAP is an industry-led activity that is focused on providing
guidance on the appropriate scope and depth of information related to
the specific portions of the safety analysis report that describe the
fundamental safety functions of the design and document the safety
analysis of the facility using the LMP-based approach. The LMP-based
approach is described in Regulatory Guide (RG) 1.233, ``Guidance for a
Technology-Inclusive, Risk-Informed, and Performance-Based Methodology
to Inform the Licensing Basis and Content of Applications for Licenses,
Certifications, and Approvals for Non-Light-Water Reactors,'' (ADAMS
Accession No. ML20091L698).
The ARCAP ISG titled ``Review of Risk-Informed, Technology-
Inclusive Advanced Reactor Applications--Roadmap'' (ARCAP Roadmap ISG)
was developed to provide a general overview of the information that
should be included in a non-LWR application. The ARCAP Roadmap ISG also
provides a review roadmap for the NRC staff with the principal purpose
of ensuring consistency, quality, and uniformity of NRC staff reviews.
The ARCAP Roadmap ISG includes references to eight other ARCAP ISGs and
a TICAP RG that are the subject of separate Federal Register notices
(FRNs) notifying the public of the issuance of these guidance
documents. Information regarding the eight other ARCAP ISGs and the
TICAP RG can be found in the table at the end of the ``Discussion''
section.
II. Discussion
The ARCAP ISG titled, Chapter 10, ``Control of Occupational Dose,''
that is the subject of this FRN, was developed because the current
application and review guidance related to control of occupational
doses is directly applicable only to light water reactors and may not
fully (or efficiently) identify the information to be included in a
technology-inclusive, risk-informed, and performance-based application
or provide a review approach for such an application.
The table in this notice provides the document description, ADAMS
accession number, and, if appropriate, the docket identification
number.
------------------------------------------------------------------------
ADAMS Regulations.gov
Document description accession No. docket ID No.
------------------------------------------------------------------------
Interim Staff Guidance DANU-ISG-2022- ML23277A139 NRC-2022-0074
01, ``Advanced Reactor Content of
Application Project, `Review of Risk-
Informed, Technology-Inclusive
Advanced Reactor Applications--
Roadmap.' ''.........................
Interim Staff Guidance DANU-ISG-2022- ML23277A140 NRC-2022-0075
02, ``Advanced Reactor Content of
Application Project Chapter 2, `Site
Information.' ''.....................
Interim Staff Guidance DANU-ISG-2022- ML23277A141 NRC-2022-0076
03, ``Advanced Reactor Content of
Application Project Chapter 9,
`Control of Routine Plant Radioactive
Effluents, Plant Contamination and
Solid Waste.' ''.....................
Interim Staff Guidance DANU-ISG-2022- ML23277A142 NRC-2022-0077
04, ``Advanced Reactor Content of
Application Project Chapter 10,
`Control of Occupational Dose.' ''...
Interim Staff Guidance DANU-ISG-2022- ML23277A143 NRC-2022-0078
05, ``Advanced Reactor Content of
Application Project Chapter 11,
`Organization and Human-System
Considerations.' ''..................
Interim Staff Guidance DANU-ISG-2022- ML23277A144 NRC-2022-0079
06, ``Advanced Reactor Content of
Application Project Chapter 12, `Post-
manufacturing and construction
Inspection, Testing, and Analysis
Program.' ''.........................
Interim Staff Guidance DANU-ISG-2022- ML23277A145 NRC-2022-0080
07, ``Advanced Reactor Content of
Application Project, `Risk-Informed
Inservice Inspection/Inservice
Testing Programs for Non-LWRs.' ''...
Interim Staff Guidance DANU-ISG-2022- ML23277A146 NRC-2022-0081
08, ``Advanced Reactor Content of
Application Project, `Risk-Informed
Technical Specifications.' ''........
Interim Staff Guidance DANU-ISG-2022- ML23277A147 NRC-2022-0082
09, ``Advanced Reactor Content of
Application Project, `Risk-Informed
Performance-Based Fire Protection
Program (for Operations).' ''........
RG 1.253, Revision 0, ``Guidance for a ML23269A222 NRC-2022-0073
Technology-Inclusive Content of
Application Methodology to Inform the
Licensing Basis and Content of
Applications for Licenses,
Certifications, and Approvals for Non-
Light-Water Reactors.''..............
Regulatory Analysis for ARCAP ISGs.... ML23093A099 NRC-2022-0074
Review of Advanced Reactor Content of ML23348A182 NRC-2022-0074
Application Project/Technology-
Inclusive Content of Application
Project Guidance.....................
Response to the Advisory Committee on ML24024A025 NRC-2022-0074
Reactor Safeguards Letter, ``Review
of Advanced Reactor Content of
Application Project/Technology-
Inclusive Content of Application
Project Guidance''...................
------------------------------------------------------------------------
[[Page 23056]]
III. Additional Information
During the 711th meeting of the Advisory Committee on Reactor
Safeguards (ACRS), December 6-7, 2023, the ACRS, the NRC staff, and
representatives of other stakeholders discussed guidance documents
related to the ARCAP and the TICAP. On December 20, 2023, the ACRS
issued a report documenting its review of these guidance documents
(ADAMS Accession No. ML23348A182). The conclusions and recommendations
in the ACRS report apply to all the ARCAP and TICAP guidance documents.
In its December 2023 report, the ACRS did not recommend any specific
changes to DANU-ISG-2022-04.
Draft DANU-ISG-2022-04, Chapter 10, ``Control of Occupational
Dose,'' was published in the Federal Register for public comment on May
25, 2023, (88 FR 33936) with a 45-day comment period. Subsequently, the
comment period was extended by 30 days as noted in the Federal Register
dated June 28, 2023 (88 FR 41985). The NRC staff received two public
comments from stakeholders. The NRC staff's evaluation and resolution
of the public comments can be found in a document located in ADAMS
under Accession No. ML23277A151.
IV. Congressional Review Act
DANU-ISG-2022-04, Chapter 10, ``Control of Occupational Dose,'' is
a rule as defined in the Congressional Review Act (5 U.S.C. 801-808).
However, the Office of Management and Budget has not found it to be a
major rule as defined in the Congressional Review Act.
V. Backfitting, Forward Fitting, and Issue Finality
DANU-ISG-2022-04 does not constitute backfitting as defined in 10
CFR 50.109, ``Backfitting,'' and as described in Management Directive
(MD) 8.4, ``Management of Backfitting, Forward Fitting, Issue Finality,
and Information Requests''; does not constitute forward fitting as that
term is defined and described in MD 8.4; and does not affect the issue
finality of any approval issued under 10 CFR part 52. The guidance
would not apply to any current licensees or applicants or existing or
requested approvals under 10 CFR part 52, and therefore its issuance
cannot be a backfit or forward fit or affect issue finality. Further,
as explained in DANU-ISG-2022-04, applicants and licensees would not be
required to comply with the positions set forth in DANU-ISG-2022-04.
Dated: March 28, 2024.
For the Nuclear Regulatory Commission.
Steven T. Lynch,
Chief, Advanced Reactor Policy Branch, Division of Advanced Reactors
and Non-Power Production and Utilization Facilities, Office of Nuclear
Reactor Regulation.
[FR Doc. 2024-07026 Filed 4-2-24; 8:45 am]
BILLING CODE 7590-01-P
