[Federal Register Volume 78, Number 165 (Monday, August 26, 2013)]
[Notices]
[Pages 52804-52806]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2013-20708]
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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.
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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 http://www.regulations.gov and search for Docket ID NRC-2013-0089. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-287-
3244; email: [email protected]. 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: [email protected].
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 http://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 http://www.nrc.gov/reading-rm/adams.html. To begin the
search, select ``ADAMS Public Documents'' and then select ``Begin Web-
based ADAMS Search.'' For problems with ADAMS, please contact the NRC's
Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-
4737, or by email to [email protected]. The ADAMS accession number
for each document referenced in this notice (if that document is
available in ADAMS) is provided the first time that a document is
referenced 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 http://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.
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Design-specific review
Section standard title ADAMS No.
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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.
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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]
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