mPower\TM\ Design-Specific Review Standard, 52804-52806 [2013-20708]

Download as PDF 52804 Federal Register / Vol. 78, No. 165 / Monday, August 26, 2013 / Notices • Minimize the burden of the collection of information on those who are to respond, including through the use of appropriate automated, electronic, mechanical, or other technological collection techniques or other forms of information technology, e.g., permitting electronic submission of responses. Agency: DOL–OSHA. Title of Collection: Additional Information Collection Requirements for Special Dipping and Coating Operations. OMB Control Number: 1218–0237. Affected Public: Private Sector— businesses or other for-profits. Total Estimated Number of Respondents: 10. Total Estimated Number of Responses: 10. Total Estimated Annual Burden Hours: 1. Total Estimated Annual Other Costs Burden: $0. Dated: August 19, 2013. Michel Smyth, Departmental Clearance Officer. [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 13:45 Aug 23, 2013 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 Antarctica and report on the science the 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 Frm 00047 Fmt 4703 Sfmt 4703 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 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: Carol.Gallagher@nrc.gov. For technical questions, contact the SUMMARY: E:\FR\FM\26AUN1.SGM 26AUN1 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 http://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 http://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 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 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 .......................................................... 13:45 Aug 23, 2013 Jkt 229001 PO 00000 Frm 00048 Fmt 4703 Sfmt 4703 52805 E:\FR\FM\26AUN1.SGM 26AUN1 ML13099A204 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 http:// 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 Jkt 229001 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). Frm 00049 Fmt 4703 Sfmt 4703 ML12319A587 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 ML13099A316 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 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: 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 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 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 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.

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