Draft Interim Staff Guidance: Advanced Reactor Content of Application Project Chapter 10, “Control of Occupational Dose”, 33936-33938 [2023-11181]
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33936
Federal Register / Vol. 88, No. 101 / Thursday, May 25, 2023 / Notices
2.318(a); or (c) if another officer has
been designated to rule on information
access issues, with that officer.
If challenges to the NRC staff
determinations are filed, these
procedures give way to the normal
process for litigating disputes
concerning access to information. The
availability of interlocutory review by
the Commission of orders ruling on
such NRC staff determinations (whether
granting or denying access) is governed
by 10 CFR 2.311.3
I. The Commission expects that the
NRC staff and presiding officers (and
any other reviewing officers) will
consider and resolve requests for access
to SUNSI, and motions for protective
orders, in a timely fashion in order to
minimize any unnecessary delays in
identifying those petitioners who have
standing and who have propounded
contentions meeting the specificity and
basis requirements in 10 CFR part 2.
The attachment to this Order
summarizes the general target schedule
for processing and resolving requests
under these procedures.
It is so ordered.
Dated: May 19, 2023.
For the Nuclear Regulatory Commission.
Brooke P. Clark,
Secretary of the Commission.
ATTACHMENT 1—GENERAL TARGET SCHEDULE FOR PROCESSING AND RESOLVING REQUESTS FOR ACCESS TO SENSITIVE
UNCLASSIFIED NON-SAFEGUARDS INFORMATION IN THIS PROCEEDING
Day
Event/activity
0 ......................
Publication of Federal Register notice of hearing or opportunity for hearing, including order with instructions for access requests.
Deadline for submitting requests for access to Sensitive Unclassified Non-Safeguards Information (SUNSI) with information:
supporting the standing of a potential party identified by name and address; describing the need for the information in order
for the potential party to participate meaningfully in an adjudicatory proceeding.
Deadline for submitting petition for intervention containing: (i) demonstration of standing; and (ii) all contentions whose formulation does not require access to SUNSI (+25 Answers to petition for intervention; +7 petitioner/requestor reply).
U.S. Nuclear Regulatory Commission (NRC) staff informs the requestor of the staff’s determination whether the request for access provides a reasonable basis to believe standing can be established and shows need for SUNSI. (NRC staff also informs any party to the proceeding whose interest independent of the proceeding would be harmed by the release of the information.) If NRC staff makes the finding of need for SUNSI and likelihood of standing, NRC staff begins document processing (preparation of redactions or review of redacted documents).
If NRC staff finds no ‘‘need’’ or no likelihood of standing, the deadline for petitioner/requestor to file a motion seeking a ruling
to reverse the NRC staff’s denial of access; NRC staff files copy of access determination with the presiding officer (or Chief
Administrative Judge or other designated officer, as appropriate). If NRC staff finds ‘‘need’’ for SUNSI, the deadline for any
party to the proceeding whose interest independent of the proceeding would be harmed by the release of the information to
file a motion seeking a ruling to reverse the NRC staff’s grant of access.
Deadline for NRC staff reply to motions to reverse NRC staff determination(s).
(Receipt +30) If NRC staff finds standing and need for SUNSI, deadline for NRC staff to complete information processing and
file motion for Protective Order and draft Non-Disclosure Agreement or Affidavit. Deadline for applicant/licensee to file NonDisclosure Agreement or Affidavit for SUNSI.
If access granted: issuance of presiding officer or other designated officer decision on motion for protective order for access to
sensitive information (including schedule for providing access and submission of contentions) or decision reversing a final
adverse determination by the NRC staff.
Deadline for filing executed Non-Disclosure Agreements or Affidavits. Access provided to SUNSI consistent with decision
issuing the protective order.
Deadline for submission of contentions whose development depends upon access to SUNSI. However, if more than 25 days
remain between the petitioner’s receipt of (or access to) the information and the deadline for filing all other contentions (as
established in the notice of hearing or notice of opportunity for hearing), the petitioner may file its SUNSI contentions by that
later deadline.
(Contention receipt +25) Answers to contentions whose development depends upon access to SUNSI.
(Answer receipt +7) Petitioner/Intervenor reply to answers.
Decision on contention admission.
10 ....................
60 ....................
20 ....................
25 ....................
30 ....................
40 ....................
A .....................
A + 3 ...............
A + 28 .............
A + 53 .............
A + 60 .............
>A + 60 ...........
Nuclear Regulatory
Commission.
The U.S. Nuclear Regulatory
Commission (NRC) is soliciting public
comment on its draft Interim Staff
Guidance (ISG) DANU–ISG–2022–04,
Chapter 10, ‘‘Control of Occupational
Dose.’’ The purpose of this proposed
ISG is to provide guidance to assist the
NRC staff in determining whether an
application for a non-light water reactor
(non-LWR) design that uses the
Licensing Modernization Project (LMP)
process meets the minimum
requirements for construction permits,
operating licenses, manufacturing
licenses, standard design approval, or
design certifications.
DATES: Submit comments by July 10,
2023. 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 on or before this date.
ADDRESSES: You may submit comments
by any of the following methods;
however, the NRC encourages electronic
comment submission through the
Federal rulemaking website.
3 Requestors should note that the filing
requirements of the NRC’s E-Filing Rule (72 FR
49139; August 28, 2007, as amended at 77 FR
46562; August 3, 2012, 78 FR 34247, June 7, 2013)
apply to appeals of NRC staff determinations
(because they must be served on a presiding officer
or the Commission, as applicable), but not to the
initial SUNSI request submitted to the NRC staff
under these procedures.
Draft guidance; request for
comment.
ACTION:
[FR Doc. 2023–11128 Filed 5–24–23; 8:45 am]
BILLING CODE 7590–01–P
SUMMARY:
NUCLEAR REGULATORY
COMMISSION
lotter on DSK11XQN23PROD with NOTICES1
[NRC–2022–0077]
Draft Interim Staff Guidance: Advanced
Reactor Content of Application Project
Chapter 10, ‘‘Control of Occupational
Dose’’
AGENCY:
VerDate Sep<11>2014
18:04 May 24, 2023
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Federal Register / Vol. 88, No. 101 / Thursday, May 25, 2023 / Notices
• 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.
• 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:
Michael Orenak, Office of Nuclear
Reactor Regulation, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001, telephone: 301–415–
3229, email: Michael.Orenak@nrc.gov.
SUPPLEMENTARY INFORMATION:
lotter on DSK11XQN23PROD with NOTICES1
I. Obtaining information and
Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC–2022–
0077 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–2022–0077.
• 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
PDR.Resource@nrc.gov. For the
convenience of the reader, instructions
about obtaining materials referenced in
this document are provided in the
‘‘Availability of Documents’’ section.
• NRC’s PDR: You may examine and
purchase copies of public documents,
by appointment, at the NRC’s PDR,
Room P1 B35, One White Flint North,
11555 Rockville Pike, Rockville,
Maryland 20852. 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–
VerDate Sep<11>2014
18:04 May 24, 2023
Jkt 259001
4737, between 8 a.m. and 4 p.m. eastern
time (ET), Monday through Friday,
except Federal holidays.
B. Submitting Comments
The NRC encourages electronic
comment submission through the
Federal rulemaking website (https://
www.regulations.gov). Please include
Docket ID NRC–2022–0077 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
The NRC 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 designs are non-LWRs,
the NRC is developing technologyinclusive, risk-informed, performancebased guidance to support the
development and review of these nonLWR applications. The proposed
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 is
developing a rule to amend 10 CFR
parts 50 and 52 (RIN 3150–Al66). The
NRC staff notes this proposed 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 draft ISG,
the NRC is developing an optional
performance-based, technology-
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33937
inclusive regulatory framework for
licensing nuclear power plants
designated as 10 CFR part 53,
‘‘Licensing and Regulation of Advanced
Nuclear Reactors,’’ (RIN 3150–AK31).
The NRC intends to revise this proposed
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
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 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 draft ISG titled ‘‘Review
of Risk-Informed, Technology Inclusive
Advanced Reactor Applications—
Roadmap’’ (ARCAP Roadmap ISG)
provides 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 draft ISGs and a
TICAP draft regulatory guide (DG) that
are the subject of separate Federal
Register notices (FRNs) requesting
comment on these guidance documents.
Information regarding the eight other
ARCAP draft ISGs and the TICAP DG
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Federal Register / Vol. 88, No. 101 / Thursday, May 25, 2023 / Notices
can be found in the ‘‘Availability of
Documents’’ section of this FRN.
III. Request for Comment
The ARCAP draft ISG titled, ‘‘Chapter
10, ‘Control of Occupational Dose,’ ’’
that is the subject of this FRN for which
the staff is seeking comment, 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,
guidance and staff review guidance is
warranted. If finalized, this ISG will
serve as the non-LWR application and
review guidance for control of
occupational dose.
IV. Availability of Documents
The table in this notice provides the
document description, ADAMS
accession number, and, if appropriate,
the docket identification number
referencing the request for public
comment on supporting documents
associated with the document that is the
subject of this FRN.
Document description
ADAMS
accession No.
Regulations.gov
docket ID No.
Draft Interim Staff Guidance DANU–ISG–2022–01 ‘‘Advanced Reactor Content of Application Project, ‘Review of Risk-Informed, Technology Inclusive Advanced Reactor Applications—Roadmap’ ’’.
Draft Interim Staff Guidance DANU–ISG–2022–02, ‘‘Advanced Reactor Content of Application Project
Chapter 2, ‘Site Information’ ’’.
Draft 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’ ’’.
Draft Interim Staff Guidance DANU–ISG–2022–04, ‘‘Advanced Reactor Content of Application Project
Chapter 10, ‘Control of Occupational Dose’ ’’.
Draft Interim Staff Guidance DANU–ISG–2022–05, ‘‘Advanced Reactor Content of Application Project
Chapter 11, ‘Organization and Human-System Considerations’ ’’.
Draft Interim Staff Guidance DANU–ISG–2022–06, ‘‘Advanced Reactor Content of Application Project
Chapter 12, ‘Post-Construction Inspection, Testing, and Analysis Program’ ’’.
Draft Interim Staff Guidance DANU–ISG–2022–07, ‘‘Advanced Reactor Content of Application Project,
‘Risk-informed Inservice Inspection/Inservice Testing’ ’’.
Draft Interim Staff Guidance DANU–ISG–2022–08, ‘‘Advanced Reactor Content of Application Project,
‘Risk-Informed Technical Specifications’ ’’.
Draft Interim Staff Guidance DANU–ISG–2022–09, ‘‘Advanced Reactor Content of Application Project,
‘Risk-informed Performance-based Fire Protection Program (for Operations)’ ’’.
DG–1404, ‘‘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-Light-Water
Reactors’’.
Regulatory Analysis for ARCAP ISGs ...............................................................................................................
ML22048B546
NRC–2022–0074
ML22048B541
NRC–2022–0075
ML22048B543
NRC–2022–0076
ML22048B544
NRC–2022–0077
ML22048B542
NRC–2022–0078
ML22048B545
NRC–2022–0079
ML22048B549
NRC–2022–0080
ML22048B548
NRC–2022–0081
ML22048B547
NRC–2022–0082
ML22076A003
NRC–2022–0073
ML23093A099
NRC–2022–0074
V. Backfitting, Forward Fitting, and
Issue Finality
lotter on DSK11XQN23PROD with NOTICES1
risk-informed, and performance-based
application or provide a review
approach for such an application. The
Chapter 10 draft ISG also refers to
several NRC-issued, approved, or
endorsed documents and the NRC is
requesting comment on this proposed
ISG’s use of those documents.
Additionally, the staff is issuing for
public comment a draft regulatory
analysis. The staff developed a
regulatory analysis to assess the value of
issuing or revising a regulatory guide as
well as alternative courses of action.
The development of both application
DANU–ISG–2022–04, if finalized,
would 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’’;
constitute forward fitting as that term is
defined and described in MD 8.4; or
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: May 22, 2023.
VerDate Sep<11>2014
18:04 May 24, 2023
Jkt 259001
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. 2023–11181 Filed 5–24–23; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2022–0080]
Draft Interim Staff Guidance: Advanced
Reactor Content of Application Project,
‘‘Risk-informed Inservice Inspection/
Inservice Testing’’
Nuclear Regulatory
Commission.
ACTION: Draft guidance; request for
comment.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is soliciting public
comment on its draft Interim Staff
Guidance (ISG) DANU–ISG–2022–07,
SUMMARY:
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Frm 00079
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‘‘Risk-informed Inservice Inspection/
Inservice Testing.’’ The purpose of this
proposed ISG is to provide guidance to
assist the NRC staff in determining
whether an application for a non-light
water reactor (non-LWR) design that
uses the Licensing Modernization
Project (LMP) process meets the
minimum requirements for construction
permits, operating licenses, combined
license, manufacturing licenses,
standard design approval, or design
certifications.
Submit comments by July 10,
2023. 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 on or before this date.
ADDRESSES: 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://www.regulations.gov and search
for Docket ID NRC–2022–0080. Address
DATES:
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]]>Agencies
[Federal Register Volume 88, Number 101 (Thursday, May 25, 2023)]
[Notices]
[Pages 33936-33938]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2023-11181]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2022-0077]
Draft Interim Staff Guidance: Advanced Reactor Content of
Application Project Chapter 10, ``Control of Occupational Dose''
AGENCY: Nuclear Regulatory Commission.
ACTION: Draft guidance; request for comment.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is soliciting
public comment on its draft Interim Staff Guidance (ISG) DANU-ISG-2022-
04, Chapter 10, ``Control of Occupational Dose.'' The purpose of this
proposed ISG is to provide guidance to assist the NRC staff in
determining whether an application for a non-light water reactor (non-
LWR) design that uses the Licensing Modernization Project (LMP) process
meets the minimum requirements for construction permits, operating
licenses, manufacturing licenses, standard design approval, or design
certifications.
DATES: Submit comments by July 10, 2023. 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 on or before
this date.
ADDRESSES: You may submit comments by any of the following methods;
however, the NRC encourages electronic comment submission through the
Federal rulemaking website.
[[Page 33937]]
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.
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: Michael Orenak, Office of Nuclear
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001, telephone: 301-415-3229, email: [email protected].
SUPPLEMENTARY INFORMATION:
I. Obtaining information and Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC-2022-0077 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-2022-0077.
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]. For the convenience of the reader,
instructions about obtaining materials referenced in this document are
provided in the ``Availability of Documents'' section.
NRC's PDR: You may examine and purchase copies of public
documents, by appointment, at the NRC's PDR, Room P1 B35, One White
Flint North, 11555 Rockville Pike, Rockville, Maryland 20852. 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.
B. Submitting Comments
The NRC encourages electronic comment submission through the
Federal rulemaking website (https://www.regulations.gov). Please
include Docket ID NRC-2022-0077 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
The NRC 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 designs are non-LWRs, the NRC is developing technology-inclusive,
risk-informed, performance-based guidance to support the development
and review of these non-LWR applications. The proposed 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 is developing a rule to
amend 10 CFR parts 50 and 52 (RIN 3150-Al66). The NRC staff notes this
proposed 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 draft ISG, the NRC is developing an optional
performance-based, technology-inclusive regulatory framework for
licensing nuclear power plants designated as 10 CFR part 53,
``Licensing and Regulation of Advanced Nuclear Reactors,'' (RIN 3150-
AK31). The NRC intends to revise this proposed 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 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 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 draft ISG titled ``Review of Risk-Informed, Technology
Inclusive Advanced Reactor Applications--Roadmap'' (ARCAP Roadmap ISG)
provides 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 draft ISGs and a
TICAP draft regulatory guide (DG) that are the subject of separate
Federal Register notices (FRNs) requesting comment on these guidance
documents. Information regarding the eight other ARCAP draft ISGs and
the TICAP DG
[[Page 33938]]
can be found in the ``Availability of Documents'' section of this FRN.
III. Request for Comment
The ARCAP draft ISG titled, ``Chapter 10, `Control of Occupational
Dose,' '' that is the subject of this FRN for which the staff is
seeking comment, 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 Chapter 10 draft ISG
also refers to several NRC-issued, approved, or endorsed documents and
the NRC is requesting comment on this proposed ISG's use of those
documents.
Additionally, the staff is issuing for public comment a draft
regulatory analysis. The staff developed a regulatory analysis to
assess the value of issuing or revising a regulatory guide as well as
alternative courses of action. The development of both application
guidance and staff review guidance is warranted. If finalized, this ISG
will serve as the non-LWR application and review guidance for control
of occupational dose.
IV. Availability of Documents
The table in this notice provides the document description, ADAMS
accession number, and, if appropriate, the docket identification number
referencing the request for public comment on supporting documents
associated with the document that is the subject of this FRN.
------------------------------------------------------------------------
ADAMS accession Regulations.gov docket
Document description No. ID No.
------------------------------------------------------------------------
Draft Interim Staff Guidance ML22048B546 NRC-2022-0074
DANU-ISG-2022-01 ``Advanced
Reactor Content of
Application Project,
`Review of Risk-Informed,
Technology Inclusive
Advanced Reactor
Applications--Roadmap' ''.
Draft Interim Staff Guidance ML22048B541 NRC-2022-0075
DANU-ISG-2022-02,
``Advanced Reactor Content
of Application Project
Chapter 2, `Site
Information' ''.
Draft Interim Staff Guidance ML22048B543 NRC-2022-0076
DANU-ISG-2022-03,
``Advanced Reactor Content
of Application Project
Chapter 9, `Control of
Routine Plant Radioactive
Effluents, Plant
Contamination and Solid
Waste' ''.
Draft Interim Staff Guidance ML22048B544 NRC-2022-0077
DANU-ISG-2022-04,
``Advanced Reactor Content
of Application Project
Chapter 10, `Control of
Occupational Dose' ''.
Draft Interim Staff Guidance ML22048B542 NRC-2022-0078
DANU-ISG-2022-05,
``Advanced Reactor Content
of Application Project
Chapter 11, `Organization
and Human-System
Considerations' ''.
Draft Interim Staff Guidance ML22048B545 NRC-2022-0079
DANU-ISG-2022-06,
``Advanced Reactor Content
of Application Project
Chapter 12, `Post-
Construction Inspection,
Testing, and Analysis
Program' ''.
Draft Interim Staff Guidance ML22048B549 NRC-2022-0080
DANU-ISG-2022-07,
``Advanced Reactor Content
of Application Project,
`Risk-informed Inservice
Inspection/Inservice
Testing' ''.
Draft Interim Staff Guidance ML22048B548 NRC-2022-0081
DANU-ISG-2022-08,
``Advanced Reactor Content
of Application Project,
`Risk-Informed Technical
Specifications' ''.
Draft Interim Staff Guidance ML22048B547 NRC-2022-0082
DANU-ISG-2022-09,
``Advanced Reactor Content
of Application Project,
`Risk-informed Performance-
based Fire Protection
Program (for Operations)'
''.
DG-1404, ``Guidance for a ML22076A003 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 ML23093A099 NRC-2022-0074
ARCAP ISGs.
------------------------------------------------------------------------
V. Backfitting, Forward Fitting, and Issue Finality
DANU-ISG-2022-04, if finalized, would 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''; constitute forward
fitting as that term is defined and described in MD 8.4; or 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: May 22, 2023.
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. 2023-11181 Filed 5-24-23; 8:45 am]
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