mPower\TM\ Design-Specific Review Standard, 52804-52806 [2013-20708]
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Federal Register / Vol. 78, No. 165 / Monday, August 26, 2013 / Notices
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[FR Doc. 2013–20690 Filed 8–23–13; 8:45 am]
BILLING CODE 4510–26–P
NATIONAL SCIENCE FOUNDATION
Notice of Permit Applications Received
Under the Antarctic Conservation Act
of 1978 (Pub. L. 95–541)
National Science Foundation.
Notice of permit applications
received under the Antarctic
Conservation Act of 1978, Public Law
95–541.
AGENCY:
ACTION:
The National Science
Foundation (NSF) is required to publish
a notice of permit applications received
to conduct activities regulated under the
Antarctic Conservation Act of 1978.
NSF has published regulations under
the Antarctic Conservation Act at Title
45 Part 670 of the Code of Federal
Regulations. This is the required notice
of permit applications received.
DATES: Interested parties are invited to
submit written data, comments, or
views with respect to this permit
application by September 25, 2013. This
application may be inspected by
interested parties at the Permit Office,
address below.
ADDRESSES: Comments should be
addressed to Permit Office, Room 755,
Division of Polar Programs, National
Science Foundation, 4201 Wilson
Boulevard, Arlington, Virginia 22230.
FOR FURTHER INFORMATION CONTACT:
Adrian Dahood, ACA Permit Officer, at
ehiers on DSK2VPTVN1PROD with NOTICES
SUMMARY:
VerDate Mar<15>2010
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Jkt 229001
the above address or ACApermits@
nsf.gov or (703) 292–7149.
SUPPLEMENTARY INFORMATION: The
National Science Foundation, as
directed by the Antarctic Conservation
Act of 1978 (Pub. L. 95–541), as
amended by the Antarctic Science,
Tourism and Conservation Act of 1996,
has developed regulations for the
establishment of a permit system for
various activities in Antarctica and
designation of certain animals and
certain geographic areas a requiring
special protection. The regulations
establish such a permit system to
designate Antarctic Specially Protected
Areas.
Application Details
1. Applicant Permit Application:
2014–009, Peter West, National Science
Foundation, Arlington Virginia.
Activity for Which Permit Is Requested
ASPA Entry; The National Science
Foundation, as U.S. taxpayer supported
government agency, routinely selects
members of the U.S. news media to visit
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foundation facilitates there. The
newsgathering process requires
journalists to visit specific sites and to
speak with the researchers conducting
science there. Any interviews,
photographs or video gathered during
visits to ASPAs would be used to inform
the general public about the importance
of the science conducted on the
continent. Visits to the ASPAs listed in
this application would take place in
conjunction with valid scientific
activities, for the express purposes of
gathering images, footage, or
information on scientific research,
general scenic locations, and interviews
with scientists working in the field.
Journalists visiting Antarctica will be
accompanied at all times by an NSF
staff ‘‘escort’’. The escort will be a
person who has years of experience
working with field parties, with
scientists and with journalists. The
escort is cognizant of—and will follow
the requirements contained in—the
ASPA management plans and the
Antarctic Conservation Act. They will
insure that every effort is made to
practice ‘‘low impact’’ documentary
procedures with regard to the natural
environment as well as to adhere to all
USAP operations and procedures.
Location
ASPA 121: Cape Royds, Ross Island.
ASPA 122: Arrival Heights, Ross Island.
ASPA 124: Cape Crozier, Ross Island.
ASPA 157: Backdoor Bay, Cape Royds
(Shackleton’s Hut), Ross Island.
PO 00000
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ASPA 158: Cape Evans (Scott’s Hut),
Ross Island.
Dates
October 1, 2013 to September 30 2018.
Nadene G. Kennedy,
Polar Coordination Specialist, Division of
Polar Programs.
[FR Doc. 2013–20704 Filed 8–23–13; 8:45 am]
BILLING CODE 7555–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2013–0089]
mPowerTM Design-Specific Review
Standard
Nuclear Regulatory
Commission.
ACTION: Design-Specific Review
Standard (DSRS) for the mPowerTM
Design; re-opening of comment period.
AGENCY:
On May 14, 2013, the U.S.
Nuclear Regulatory Commission (NRC)
published a request for public comment
on the DSRS for the mPowerTM design
(mPowerTM DSRS). The purpose of the
mPowerTM DSRS is to more fully
integrate the use of risk insights into the
review of a design certification (DC), an
early site permit (ESP) or a combined
license (COL) that incorporates the
mPowerTM design. The public comment
period was originally scheduled to close
on August 16, 2013. Generation mPower
submitted a letter on August 8, 2013
(ADAMS Accession No. ML13224A163),
requesting an extension of the public
comment period until September 16,
2012, on specific sections of the
mPowerTM DSRS. The NRC has decided
to re-open the public comment period
on those specific sections of the
mPowerTM DSRS to allow more time for
members of the public to assemble their
comments on those sections.
DATES: The comment period has been
re-opened and now closes on September
16, 2013. 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 (unless
this document describes a different
method for submitting comments on a
specific subject):
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2013–0089. Address
questions about NRC dockets to Carol
Gallagher; telephone: 301–287–3244;
email: Carol.Gallagher@nrc.gov. For
technical questions, contact the
SUMMARY:
E:\FR\FM\26AUN1.SGM
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Federal Register / Vol. 78, No. 165 / Monday, August 26, 2013 / Notices
individual(s) listed in the FOR FURTHER
INFORMATION CONTACT section of this
document.
• Mail comments to: Cindy Bladey,
Chief, Rules, Announcements, and
Directives Branch (RADB), Office of
Administration, Mail Stop: 3WFN 06–
44M, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001.
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:
Yanely Malave, Office of New Reactors,
U.S. Nuclear Regulatory Commission,
Washington, DC 20555–0001; telephone:
301–415–1519 or email:
Yanely.Malave@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Accessing Information and
Submitting Comments
ehiers on DSK2VPTVN1PROD with NOTICES
A. Accessing Information
Please refer to Docket ID NRC–2013–
0089 when contacting the NRC about
the availability of information regarding
this document. You may access
publicly-available information related to
this action by the following methods:
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2013–0089.
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): You may access publiclyavailable documents online in the NRC
Library at https://www.nrc.gov/readingrm/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. 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 and also in the
table included in this notice. The DSRS
sections are available in ADAMS under
the corresponding accession number as
describe in Section II, ‘‘Further
Information,’’ of this notice.
• 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–
0089 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
you do not want to be publicly
disclosed in your comment submission.
The NRC posts all comment
submissions at https://
www.regulations.gov as well as entering
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
A. Background
In 2010, the Commission provided
direction to the staff on the preparation
for, and review of, small modular
reactor (SMR) applications, with a nearterm focus on integral pressurized water
reactor (iPWR) designs. The
Commission directed the staff to more
fully integrate the use of risk insights
into pre-application activities and the
review of applications and, consistent
with regulatory requirements and
Commission policy statements, to align
the review focus and resources to risksignificant structures, systems, and
components and other aspects of the
design that contribute most to safety in
order to enhance the effectiveness and
efficiency of the review process. The
Commission directed the staff to
develop a design-specific, risk-informed
review plan for each SMR design to
address pre-application and application
Section
3.7.1
3.7.2
3.7.3
3.8.2
3.8.3
...............................
...............................
...............................
...............................
...............................
VerDate Mar<15>2010
review activities. An important part of
this review plan is the DSRS. This DSRS
for the mPowerTM design is the result of
the implementation of the Commission’s
direction.
B. DSRS for the mPowerTM Design
As part of the mPowerTM DSRS, the
NRC’s Office of New Reactors has issued
the mPowerTM Design-Specific Review
Standard Scope and Safety Review
Matrix (ADAMS Accession No.
ML13088A252) to reflect the integration
of risk insights into the review of
applications submitted for the
mPowerTM DC and ESPs or COLs that
incorporate the mPowerTM design under
part 52 of Title 10 of the Code of Federal
Regulations. The mPowerTM DSRS
reflects current staff review methods
and practices based on the integration of
risk insights and, where appropriate,
lessons learned from NRC reviews of DC
and COL applications completed since
the last revision of the Standard Review
Plan.
C. Re-Opening of Comment Period
On May 14, 2013 (78 FR 28258), the
NRC published a request for public
comment on the mPowerTM DSRS. The
public comment period was originally
scheduled to close on August 16, 2013.
Generation mPower submitted a letter
on August 8, 2013 (ADAMS Accession
No. ML13224A163), requesting an
extension of the public comment period
until September 16, 2013, on specific
sections of the mPowerTM DSRS. The
NRC has decided to re-open the public
comment period on those specific
sections of the mPowerTM DSRS to
allow more time for members of the
public to assemble their comments on
those sections. The NRC did not receive
a request to extend the comment period
on the additional sections in the May
14, 2013, request for public comment;
and believes the original 90-day public
comment period afforded for those
sections is sufficient.
Specifically, we request comment on
the sufficiency of the proposed
technical content of the individual
mPowerTM DSRS sections, identified in
the following table, that were revised or
developed to incorporate design-specific
review guidance based on features of the
mPowerTM reactor design.
Design-specific review standard title
ADAMS No.
Seismic Design Parameters ................................................................................................................
Seismic System Analysis ....................................................................................................................
Seismic Subsystem Analysis ...............................................................................................................
Steel Containment ...............................................................................................................................
Concrete and Steel Internal Structures of Steel Containments ..........................................................
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ML13099A205
ML13099A209
ML13099A298
ML13099A312
52806
Federal Register / Vol. 78, No. 165 / Monday, August 26, 2013 / Notices
Section
Design-specific review standard title
3.8.4 ...............................
3.8.5 ...............................
15.0 ................................
15.0.2 .............................
15.0.3 .............................
15.1.5 .............................
15.2.1–15.2.5 .................
Other Seismic Category I Structures ..................................................................................................
Foundations .........................................................................................................................................
Introduction—Transient and Accident Analyses .................................................................................
Review of Transient and Accident Analysis Methods .........................................................................
Design Basis Accident Radiological Consequence Analyses for Advanced Light Water Reactors ...
Steam System Piping Failures Inside and Outside of Containment ...................................................
Loss of External Load; Turbine Trip; Loss of Condenser Vacuum; Closure of Main Steam Isolation
Valve (BWR); and Steam Pressure Regulator Failure (Closed).
Loss of Nonemergency AC Power to the Station Auxiliaries .............................................................
Loss of Normal Feedwater Flow .........................................................................................................
Feedwater System Pipe Breaks Inside and Outside Containment (PWR) .........................................
Loss of Forced Reactor Coolant Flow Including Trip of Pump Motor and Flow Controller Malfunctions.
Reactor Coolant Pump Rotor Seizure and Reactor Coolant Pump Shaft Break ...............................
Uncontrolled Control Rod Assembly Withdrawal from a Subcritical or Low Power Startup Condition.
Uncontrolled Control Rod Assembly Withdrawal at Power .................................................................
Startup of an Inactive Pump or Pumps at an Incorrect Temperature, and Flow Controller Malfunction causing an Increase in Core Flow Rate.
Inadvertent Operation of ECCS and Reactor Coolant Inventory and Purification System (RCI) Malfunction that Increases Reactor Coolant Inventory.
Inadvertent Opening of a Pressurizer Safety Valve, or an Automatic Depressurization Valve .........
Loss of Coolant Accidents Resulting From Spectrum of Postulated Piping Breaks Within the Reactor Coolant Pressure Boundary.
Anticipated Transients Without Scram ................................................................................................
15.2.6 .............................
15.2.7 .............................
15.2.8 .............................
15.3.1–15.3.2 .................
15.3.3–15.3.4 .................
15.4.1 .............................
15.4.2 .............................
15.4.10 ...........................
15.5.1–15.5.2 .................
15.6.1 .............................
15.6.5 .............................
15.8 ................................
Dated at Rockville, Maryland, this 20th day
of August, 2013.
For the Nuclear Regulatory Commission.
Yanely Malave,
Project Manager, Small Modular Reactor
Licensing Branch 1, Division of Advanced
Reactors and Rulemaking, Office of New
Reactors.
[FR Doc. 2013–20708 Filed 8–23–13; 8:45 am]
BILLING CODE 7590–01–P
POSTAL REGULATORY COMMISSION
[Docket No. RM2013–6; Order No. 1814]
Periodic Reporting (Proposals One
Through Five)
Postal Regulatory Commission.
Notice.
AGENCY:
ACTION:
The Commission is noticing a
recent Postal Service filing requesting
an informal proceeding to consider
changes in four analytical method
changes for use in periodic reporting.
This notice informs the public of the
filing, invites public comment, and
takes other administrative steps.
DATES: Comments are due: September 9,
2013. Reply comments are due:
September 19, 2013.
ADDRESSES: Submit comments
electronically via the Commission’s
Filing Online system at https://
www.prc.gov. Those who cannot submit
comments electronically should contact
the person identified in the FOR FURTHER
INFORMATION CONTACT section by
telephone for advice on filing
alternatives.
ehiers on DSK2VPTVN1PROD with NOTICES
SUMMARY:
VerDate Mar<15>2010
13:45 Aug 23, 2013
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FOR FURTHER INFORMATION CONTACT:
Stephen L. Sharfman, General Counsel,
at 202–789–6820.
SUPPLEMENTARY INFORMATION:
Table of Contents
of the United States Postal Service for
the Initiation of a Proceeding to Consider Proposed
Changes in Analytical Principles (Proposals One
through Four), August 16, 2013 (Petition).
2 Id. at 1; see also Docket No. ACR2012,
Responses of the United States Postal Service to
Commission Requests for Additional Information in
FY 2012 Annual Compliance Determination, Item 3,
June 26, 2013 (Proposal Five).
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ML12250A248
ML12319A668
ML12319A585
ML12319A586
ML12240A005
ML12242A102
ML12261A399
ML12319A575
ML12250A318
ML12319A576
ML12319A577
changes identified in response to the
Commission directive in Docket No.
ACR2012, Item 3. Id. This request will
be labeled as Proposal Five and
reviewed as part of this docket.
A. Proposal One: New Formula and
Location for Alaska Air Adjustment
Factor
I. Introduction
On August 16, 2013, the Postal
Service filed a petition pursuant to 39
CFR 3050.11 requesting that the
Commission initiate an informal
rulemaking proceeding to consider
changes in four analytical methods for
use in periodic reporting.1 The Petition
labels the proposed analytical method
changes filed in this docket as Proposals
One through Four. In addition, the
Petition requests clarification
concerning the status of a proposal that
the Postal Service filed in response to a
Commission directive in Docket No.
ACR2012 regarding distribution of
settlement costs within certain Global
Plus Negotiated Service Agreement
(NSA) products.2 This request for
clarification will be treated as a petition
pursuant to 39 CFR 3050.11 requesting
that the Commission initiate an informal
rulemaking proceeding to consider the
PO 00000
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ML13099A319
ML12275A026
ML12207A098
ML12257A226
ML12207A108
ML12319A584
II. Proposals
I. Introduction
II. Proposals
III. Notice and Comment
IV. Ordering Paragraphs
1 Petition
ADAMS No.
The Postal Service proposes a simpler
method for calculating the Alaska Air
Adjustment Factor. In addition, the
Postal Service proposes to implement
the Alaska Air Adjustment Factor
within the Cost Segment 14 model,
rather than with the Cost and Revenue
Analysis (CRA) model. It asserts that the
current method for calculating the
Alaska Air Adjustment Factor is
unnecessarily complex, and since the
current method was established, postal
operational data have improved
significantly. Thus, it contends, that the
proposal is a more accurate and more
easily updateable ratio of highway to air
costs. It also believes that implementing
the proposed change in the Cost
Segment 14 workbook, rather than in
the CRA model where it is currently
located, would help increase
transparency. See Petition at 2–3.
B. Proposal Two: New Set of
Distribution Factors for Alaska NonPreferential, Alaska Preferential,
Hawaii, and Air Taxi Cost Pools in Cost
Segment 14
The Postal Service proposes a single
set of distribution factors to assign
relevant costs from the Non-Preferential
E:\FR\FM\26AUN1.SGM
26AUN1
]]>Agencies
[Federal Register Volume 78, Number 165 (Monday, August 26, 2013)]
[Notices]
[Pages 52804-52806]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2013-20708]
=======================================================================
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2013-0089]
mPower\TM\ Design-Specific Review Standard
AGENCY: Nuclear Regulatory Commission.
ACTION: Design-Specific Review Standard (DSRS) for the mPower\TM\
Design; re-opening of comment period.
-----------------------------------------------------------------------
SUMMARY: On May 14, 2013, the U.S. Nuclear Regulatory Commission (NRC)
published a request for public comment on the DSRS for the mPower\TM\
design (mPower\TM\ DSRS). The purpose of the mPower\TM\ DSRS is to more
fully integrate the use of risk insights into the review of a design
certification (DC), an early site permit (ESP) or a combined license
(COL) that incorporates the mPower\TM\ design. The public comment
period was originally scheduled to close on August 16, 2013. Generation
mPower submitted a letter on August 8, 2013 (ADAMS Accession No.
ML13224A163), requesting an extension of the public comment period
until September 16, 2012, on specific sections of the mPower\TM\ DSRS.
The NRC has decided to re-open the public comment period on those
specific sections of the mPower\TM\ DSRS to allow more time for members
of the public to assemble their comments on those sections.
DATES: The comment period has been re-opened and now closes on
September 16, 2013. 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
(unless this document describes a different method for submitting
comments on a specific subject):
Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC-2013-0089. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-287-
3244; email: Carol.Gallagher@nrc.gov. For technical questions, contact
the
[[Page 52805]]
individual(s) listed in the FOR FURTHER INFORMATION CONTACT section of
this document.
Mail comments to: Cindy Bladey, Chief, Rules,
Announcements, and Directives Branch (RADB), Office of Administration,
Mail Stop: 3WFN 06-44M, U.S. Nuclear Regulatory Commission, Washington,
DC 20555-0001.
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: Yanely Malave, Office of New Reactors,
U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001;
telephone: 301-415-1519 or email: Yanely.Malave@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Accessing Information and Submitting Comments
A. Accessing Information
Please refer to Docket ID NRC-2013-0089 when contacting the NRC
about the availability of information regarding this document. You may
access publicly-available information related to this action by the
following methods:
Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC-2013-0089.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may access publicly-available documents online in the NRC
Library 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. 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 and also in the table included in this notice. The DSRS
sections are available in ADAMS under the corresponding accession
number as describe in Section II, ``Further Information,'' of this
notice.
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-2013-0089 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 you do not want to be publicly disclosed in your
comment submission. The NRC posts all comment submissions at https://www.regulations.gov as well as entering 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
A. Background
In 2010, the Commission provided direction to the staff on the
preparation for, and review of, small modular reactor (SMR)
applications, with a near-term focus on integral pressurized water
reactor (iPWR) designs. The Commission directed the staff to more fully
integrate the use of risk insights into pre-application activities and
the review of applications and, consistent with regulatory requirements
and Commission policy statements, to align the review focus and
resources to risk-significant structures, systems, and components and
other aspects of the design that contribute most to safety in order to
enhance the effectiveness and efficiency of the review process. The
Commission directed the staff to develop a design-specific, risk-
informed review plan for each SMR design to address pre-application and
application review activities. An important part of this review plan is
the DSRS. This DSRS for the mPower\TM\ design is the result of the
implementation of the Commission's direction.
B. DSRS for the mPower\TM\ Design
As part of the mPower\TM\ DSRS, the NRC's Office of New Reactors
has issued the mPower\TM\ Design-Specific Review Standard Scope and
Safety Review Matrix (ADAMS Accession No. ML13088A252) to reflect the
integration of risk insights into the review of applications submitted
for the mPower\TM\ DC and ESPs or COLs that incorporate the mPower\TM\
design under part 52 of Title 10 of the Code of Federal Regulations.
The mPower\TM\ DSRS reflects current staff review methods and practices
based on the integration of risk insights and, where appropriate,
lessons learned from NRC reviews of DC and COL applications completed
since the last revision of the Standard Review Plan.
C. Re-Opening of Comment Period
On May 14, 2013 (78 FR 28258), the NRC published a request for
public comment on the mPower\TM\ DSRS. The public comment period was
originally scheduled to close on August 16, 2013. Generation mPower
submitted a letter on August 8, 2013 (ADAMS Accession No. ML13224A163),
requesting an extension of the public comment period until September
16, 2013, on specific sections of the mPower\TM\ DSRS. The NRC has
decided to re-open the public comment period on those specific sections
of the mPower\TM\ DSRS to allow more time for members of the public to
assemble their comments on those sections. The NRC did not receive a
request to extend the comment period on the additional sections in the
May 14, 2013, request for public comment; and believes the original 90-
day public comment period afforded for those sections is sufficient.
Specifically, we request comment on the sufficiency of the proposed
technical content of the individual mPower\TM\ DSRS sections,
identified in the following table, that were revised or developed to
incorporate design-specific review guidance based on features of the
mPower\TM\ reactor design.
------------------------------------------------------------------------
Design-specific review
Section standard title ADAMS No.
------------------------------------------------------------------------
3.7.1......................... Seismic Design ML13099A204
Parameters.
3.7.2......................... Seismic System ML13099A205
Analysis.
3.7.3......................... Seismic Subsystem ML13099A209
Analysis.
3.8.2......................... Steel Containment..... ML13099A298
3.8.3......................... Concrete and Steel ML13099A312
Internal Structures
of Steel Containments.
[[Page 52806]]
3.8.4......................... Other Seismic Category ML13099A316
I Structures.
3.8.5......................... Foundations........... ML13099A319
15.0.......................... Introduction--Transien ML12275A026
t and Accident
Analyses.
15.0.2........................ Review of Transient ML12207A098
and Accident Analysis
Methods.
15.0.3........................ Design Basis Accident ML12257A226
Radiological
Consequence Analyses
for Advanced Light
Water Reactors.
15.1.5........................ Steam System Piping ML12207A108
Failures Inside and
Outside of
Containment.
15.2.1-15.2.5................. Loss of External Load; ML12319A584
Turbine Trip; Loss of
Condenser Vacuum;
Closure of Main Steam
Isolation Valve
(BWR); and Steam
Pressure Regulator
Failure (Closed).
15.2.6........................ Loss of Nonemergency ML12319A587
AC Power to the
Station Auxiliaries.
15.2.7........................ Loss of Normal ML12250A248
Feedwater Flow.
15.2.8........................ Feedwater System Pipe ML12319A668
Breaks Inside and
Outside Containment
(PWR).
15.3.1-15.3.2................. Loss of Forced Reactor ML12319A585
Coolant Flow
Including Trip of
Pump Motor and Flow
Controller
Malfunctions.
15.3.3-15.3.4................. Reactor Coolant Pump ML12319A586
Rotor Seizure and
Reactor Coolant Pump
Shaft Break.
15.4.1........................ Uncontrolled Control ML12240A005
Rod Assembly
Withdrawal from a
Subcritical or Low
Power Startup
Condition.
15.4.2........................ Uncontrolled Control ML12242A102
Rod Assembly
Withdrawal at Power.
15.4.10....................... Startup of an Inactive ML12261A399
Pump or Pumps at an
Incorrect
Temperature, and Flow
Controller
Malfunction causing
an Increase in Core
Flow Rate.
15.5.1-15.5.2................. Inadvertent Operation ML12319A575
of ECCS and Reactor
Coolant Inventory and
Purification System
(RCI) Malfunction
that Increases
Reactor Coolant
Inventory.
15.6.1........................ Inadvertent Opening of ML12250A318
a Pressurizer Safety
Valve, or an
Automatic
Depressurization
Valve.
15.6.5........................ Loss of Coolant ML12319A576
Accidents Resulting
From Spectrum of
Postulated Piping
Breaks Within the
Reactor Coolant
Pressure Boundary.
15.8.......................... Anticipated Transients ML12319A577
Without Scram.
------------------------------------------------------------------------
Dated at Rockville, Maryland, this 20th day of August, 2013.
For the Nuclear Regulatory Commission.
Yanely Malave,
Project Manager, Small Modular Reactor Licensing Branch 1, Division of
Advanced Reactors and Rulemaking, Office of New Reactors.
[FR Doc. 2013-20708 Filed 8-23-13; 8:45 am]
BILLING CODE 7590-01-P
