mPower\TM\ Design-Specific Review Standard, 28258-28262 [2013-11394]

Download as PDF 28258 Federal Register / Vol. 78, No. 93 / Tuesday, May 14, 2013 / Notices allowed outage times for inoperable instrumentation for Neutron Flux (Extended Range) and Neutron Flux— Startup Rate (Extended Range) (Instrument Nos. 19 and 23). The required actions have been revised to enhance plant reliability by reducing exposure to unnecessary shutdowns and increase operational flexibility by allowing more time to implement required repairs for inoperable instrumentation. The changes are consistent with requirements generically approved as part of NUREG– 1431, Standard Technical Specifications, Westinghouse Plants, Revision 4 (TS 3.3.3, ‘‘Post Accident Monitoring (PAM) Instrumentation’’). Date of issuance: April 25, 2013. Effective date: As of the date of issuance and shall be implemented within 90 days of issuance. Amendment Nos.: Unit 1—200; Unit 2—198. Facility Operating License Nos. NPF– 76 and NPF–80: The amendments revised the Facility Operating Licenses and Technical Specifications. Date of initial notice in Federal Register: October 2, 2012 (77 FR 60154). The supplemental letter dated April 15, 2013, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staff’s original proposed no significant hazards consideration determination as published in the Federal Register. The Commission’s related evaluation of the amendments is contained in a Safety Evaluation dated April 25, 2013. No significant hazards consideration comments received: No. Dated at Rockville, Maryland, this 6th day of May 2013. For the Nuclear Regulatory Commission. Michele G. Evans, Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2013–11272 Filed 5–13–13; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION mstockstill on DSK4VPTVN1PROD with NOTICES Sunshine Act Meetings AGENCY HOLDING THE MEETINGS: Nuclear Regulatory Commission, [NRC–2013– 0001]. DATE: Weeks of May 13, 20, 27, June 3, 10, 17, 2013. PLACE: Commissioners’ Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. VerDate Mar<15>2010 16:52 May 13, 2013 Jkt 229001 Week of May 13, 2013 There are no meetings scheduled for the week of May 13, 2013. Week of May 20, 2013—Tentative Monday, May 20, 2013 9:30 a.m. Briefing on Human Capital and Equal Employment Opportunity (EEO) (Public Meeting) (Contact: Kristin Davis, 301–287–0707). This meeting will be webcast live at the Web address—www.nrc.gov. Week of May 27, 2013—Tentative Tuesday, May 28, 2013 10:00 a.m. Briefing on Security Issues (Closed—Ex. 1). Wednesday, May 29, 2013 9:00 a.m. Briefing on Results of the Agency Action Review Meeting (AARM) (Public Meeting) (Contact: Rani Franovich, 301–415–1868). This meeting will be webcast live at the Web address—www.nrc.gov. Week of June 3, 2013—Tentative There are no meetings scheduled for the week of June 3, 2013. Week of June 10, 2013—Tentative There are no meetings scheduled for the week of June 10, 2013. Week of June 17, 2013—Tentative There are no meetings scheduled for the week of June 17, 2013. * * * * * *The schedule for Commission meetings is subject to change on short notice. To verify the status of meetings, call (recording)—301–415–1292. Contact person for more information: Rochelle Bavol, 301–415–1651. * * * * * The NRC Commission Meeting Schedule can be found on the Internet at: http://www.nrc.gov/public-involve/ public-meetings/schedule.html. * * * * * The NRC provides reasonable accommodation to individuals with disabilities where appropriate. If you need a reasonable accommodation to participate in these public meetings, or need this meeting notice or the transcript or other information from the public meetings in another format (e.g. braille, large print), please notify Kimberly Meyer, NRC Disability Program Manager, at 301–287–0727, or by email at kimberly.meyerchambers@nrc.gov. Determinations on requests for reasonable accommodation will be made on a case-by-case basis. * * * * * This notice is distributed electronically to subscribers. If you no PO 00000 Frm 00077 Fmt 4703 Sfmt 4703 longer wish to receive it, or would like to be added to the distribution, please contact the Office of the Secretary, Washington, DC 20555 (301–415–1969), or send an email to darlene.wright@nrc.gov. Dated: May 9, 2013. Rochelle C. Bavol, Policy Coordinator, Office of the Secretary. [FR Doc. 2013–11542 Filed 5–10–13; 4:15 pm] BILLING CODE 7590–01–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; request for comment. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on the Design-Specific Review Standard (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. DATES: Submit comments by August 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 comment 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: 301–492–3668; email: Carol.Gallagher@nrc.gov. For technical questions, contact the 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: TWB–05– B01M, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001. • Fax comments to: RADB at 301– 492–3446. SUMMARY: E:\FR\FM\14MYN1.SGM 14MYN1 Federal Register / Vol. 78, No. 93 / Tuesday, May 14, 2013 / Notices 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: Ms. Yanely Malave, Office of New Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001; telephone: 301–415–1519 or email at 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 information related to this document, which the NRC possesses and is publicly-available, 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 mPowerTM DSRS Scope and Safety Review Matrix is available in ADAMS under Accession No. ML13088A252. • 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 28259 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 Design-Specific Review Standard. This DSRS for the mPowerTM design is the result of the implementation of the Commission’s direction. B. Design-Specific Review Standard (DSRS) for the mPowerTM Design As part of the mPowerTM DesignSpecific Review Plan, the Office of New Reactors has issued the mPowerTM Design-Specific Review Standard Scope and Safety Review Matrix 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 10 CFR Part 52. 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. The NRC staff is issuing this notice to solicit public comment on the mPowerTM DSRS Scope and Safety Review Matrix (Matrix), and the individual mPowerTM-specific DSRS sections. Specifically, we request comment on the sufficiency of the proposed mPowerTM review scope encompassed by the Matrix, and comment on technical content of the individual mPowerTM DSRS sections identified in the table below that were revised or developed to incorporate design-specific review guidance based on features of the mPowerTM reactor design. We are not, however, soliciting detailed technical comments on NUREG–0800 Standard Review Plan sections that are designated with the applicability ‘‘A) Use SRP Section as-is . . .’’ in the Matrix unless their adequacy for review of the mPowerTM design is in question. mstockstill on DSK4VPTVN1PROD with NOTICES Section Design-specific review standard title ADAMS No. Matrix ............................. 2.4.0 ............................... 2.4.1 ............................... 2.4.2 ............................... 2.4.3 ............................... 2.4.4 ............................... 2.4.5 ............................... 2.4.6 ............................... 2.4.7 ............................... 2.4.9 ............................... 2.4.10 ............................. 2.4.12 ............................. mPowerTM DSRS Scope and Safety Review Matrix .............................................................................. Hydrology Review ................................................................................................................................... Hydrologic Description ............................................................................................................................ Floods ...................................................................................................................................................... Probable Maximum Flood (PMF) on Streams and Rivers ..................................................................... Potential Dam Failures ............................................................................................................................ Probable Maximum Surge and Seiche Flooding .................................................................................... Probable Maximum Tsunami Flooding ................................................................................................... Ice Effects ............................................................................................................................................... Channel Diversions ................................................................................................................................. Flooding Protection Requirements .......................................................................................................... Groundwater ............................................................................................................................................ ML13088A252 ML12355A691 ML12221A023 ML12221A024 ML12221A025 ML12221A026 ML12221A027 ML12221A028 ML12221A017 ML12221A018 ML12221A019 ML12221A020 VerDate Mar<15>2010 16:52 May 13, 2013 Jkt 229001 PO 00000 Frm 00078 Fmt 4703 Sfmt 4703 E:\FR\FM\14MYN1.SGM 14MYN1 28260 Federal Register / Vol. 78, No. 93 / Tuesday, May 14, 2013 / Notices Section Design-specific review standard title ADAMS No. 2.4.13 ............................. 2.4.14 ............................. 3.2.1 ............................... 3.2.2 ............................... 3.3.1 ............................... 3.3.2 ............................... 3.4.1 ............................... 3.4.2 ............................... 3.5.1.1 ............................ 3.5.1.2 ............................ 3.5.1.3 ............................ 3.5.1.4 ............................ 3.5.1.5 ............................ 3.5.1.6 ............................ 3.5.2 ............................... 3.5.3 ............................... 3.6.2 ............................... Accidental Releases of Radioactive Liquid Effluents in Ground and Surface Waters ........................... Technical Specifications and Emergency Operation Requirements ...................................................... Seismic Classification ............................................................................................................................. System Quality Group Classification ...................................................................................................... Severe Wind Loading .............................................................................................................................. Extreme Wind Loads (Tornado and Hurricane Loads) ........................................................................... Internal Flood Protection for Onsite Equipment Failure ......................................................................... Protection of Structures Against Flood From External Sources ............................................................. Internally Generated Missiles (Outside Containment) ............................................................................ Internally Generated Missiles (Inside Containment) ............................................................................... Turbine Missiles ...................................................................................................................................... Missiles Generated by Extreme Winds ................................................................................................... Site Proximity Missiles (Except Aircraft) ................................................................................................. Aircraft Hazards ...................................................................................................................................... Structures, Systems, and Components To Be Protected From Externally Generated Missiles ............ Barrier Design Procedures ...................................................................................................................... Determination of Rupture Locations and Dynamic Effects Associated with the Postulated Rupture of Piping. Seismic Design Parameters .................................................................................................................... Seismic System Analysis ........................................................................................................................ Seismic Subsystem Analysis .................................................................................................................. Steel Containment ................................................................................................................................... Concrete and Steel Internal Structures of Steel Containments ............................................................. Other Seismic Category I Structures ...................................................................................................... Foundations ............................................................................................................................................. Special Topics for Mechanical Components .......................................................................................... Control Rod Drive Systems .................................................................................................................... Reactor Pressure Vessel Internals ......................................................................................................... Functional Design, Qualification, and Inservice Testing Programs for Pumps, Valves, and Dynamic Restraints. Environmental Qualification of Mechanical and Electrical Equipment ................................................... Threaded Fasteners—ASME Code Class 1, 2, and 3 ........................................................................... Postulated Rupture Locations in Fluid System Piping Inside and Outside Containment ...................... Fuel System Design ................................................................................................................................ Nuclear Design ........................................................................................................................................ Thermal and Hydraulic Design ............................................................................................................... Control Rod Drive Structural Materials ................................................................................................... Reactor Internal and Core Support Structure Materials ......................................................................... Functional Design of Control Rod Drive System .................................................................................... Compliance With the Codes and Standards Rule, 10 CFR 50.55a ....................................................... Applicable Code Cases ........................................................................................................................... Reactor Coolant Pressure Boundary Materials ...................................................................................... Reactor Coolant Pressure Boundary Leakage Detection ....................................................................... Reactor Vessel Materials ........................................................................................................................ Pressure-Temperature Limits, Upper-shelf Energy, and Pressurized Thermal Shock .......................... Reactor Vessel Integrity .......................................................................................................................... Steam Generator Materials ..................................................................................................................... Steam Generator Program ...................................................................................................................... Residual Heat Removal (RHR) System .................................................................................................. Design Requirements of the Residual Heat Removal System ............................................................... Engineered Safety Features Materials ................................................................................................... Protective Coating Systems (Paints)—Organic Materials ...................................................................... Containment Functional Design .............................................................................................................. mPower iPWR Containment ................................................................................................................... Subcompartment Analysis ...................................................................................................................... Mass and Energy Release Analysis for Postulated Loss of Coolant Accidents .................................... Mass and Energy Release Analysis for Postulated Secondary System Pipe Ruptures ........................ Containment Heat Removal Systems ..................................................................................................... Containment Isolation System ................................................................................................................ Combustible Gas Control in Containment .............................................................................................. Containment Leakage Testing ................................................................................................................ Fracture Prevention of Containment Pressure Boundary ....................................................................... Control Room Habitability System .......................................................................................................... Inservice Inspection and Testing of Class 2 and 3 Components ........................................................... PH for Emergency Coolant Water for Pressurized Water Reactors ...................................................... Minimum Containment Pressure Model for PWR ECCS Performance Evaluation ................................ Containment Purging During Normal Plant Operations .......................................................................... Instrumentation and Controls—Introduction and Overview of Review Process ..................................... Instrumentation and Controls—Fundamental Design Principles ............................................................ Instrumentation and Controls—System Characteristics ......................................................................... Instrumentation and Controls—Hazard Analysis .................................................................................... Instrumentation and Controls—System Architecture .............................................................................. Instrumentation and Controls—Simplicity ............................................................................................... Instrumentation and Controls—References ............................................................................................ ML12221A021 ML12221A022 ML12272A013 ML12272A015 ML12324A156 ML12324A166 ML12312A148 ML12324A190 ML12313A158 ML12313A396 ML12272A209 ML12313A399 ML12318A151 ML12318A198 ML12313A457 ML12222A003 ML12230A013 mstockstill on DSK4VPTVN1PROD with NOTICES 3.7.1 3.7.2 3.7.3 3.8.2 3.8.3 3.8.4 3.8.5 3.9.1 3.9.4 3.9.5 3.9.6 ............................... ............................... ............................... ............................... ............................... ............................... ............................... ............................... ............................... ............................... ............................... 3.11 ................................ 3.13 ................................ BTP 3–4 ......................... 4.2 .................................. 4.3 .................................. 4.4 .................................. 4.5.1 ............................... 4.5.2 ............................... 4.6 .................................. 5.2.1.1 ............................ 5.2.1.2 ............................ 5.2.3 ............................... 5.2.5 ............................... 5.3.1 ............................... 5.3.2 ............................... 5.3.3 ............................... 5.4.2.1 ............................ 5.4.2.2 ............................ 5.4.7 ............................... BTP 5–4 ......................... 6.1.1 ............................... 6.1.2 ............................... 6.2.1 ............................... 6.2.1.1 ............................ 6.2.1.2 ............................ 6.2.1.3 ............................ 6.2.1.4 ............................ 6.2.2 ............................... 6.2.4 ............................... 6.2.5 ............................... 6.2.6 ............................... 6.2.7 ............................... 6.4 .................................. 6.6 .................................. BTP 6–1 ......................... BTP 6–2 ......................... BTP 6–4 ......................... 7.0 (DSRS) ..................... 7.1 (DSRS) ..................... 7.2 (DSRS) ..................... 7.0 APP A (DSRS) ......... 7.0 APP B (DSRS) ......... 7.0 APP C (DSRS) ........ 7.0 APP D (DSRS) ........ VerDate Mar<15>2010 16:52 May 13, 2013 Jkt 229001 PO 00000 Frm 00079 Fmt 4703 Sfmt 4703 E:\FR\FM\14MYN1.SGM 14MYN1 ML13099A204 ML13099A205 ML13099A209 ML13099A298 ML13099A312 ML13099A316 ML13099A319 ML12272A018 ML12272A020 ML12272A077 ML12272A217 ML12277A018 ML12272A214 ML12272A102 ML12235A168 ML12353A188 ML12319A580 ML12326A740 ML12272A006 ML12353A182 ML12272A091 ML12272A096 ML12272A007 ML12313A468 ML12272A008 ML12272A009 ML12272A010 ML12272A244 ML12272A245 ML12319A582 ML12275A020 ML12276A107 ML12272A246 ML12276A117 ML12227A377 ML12230A014 ML12230A034 ML12230A037 ML12276A118 ML12276A120 ML12276A124 ML12276A127 ML12278A103 ML12272A225 ML12284A064 ML12222A198 ML12227A380 ML12227A384 ML12314A197 ML12313A479 ML12314A201 ML12318A200 ML12318A201 ML12318A204 ML12318A205 Federal Register / Vol. 78, No. 93 / Tuesday, May 14, 2013 / Notices 28261 Section Design-specific review standard title ADAMS No. 8.1 .................................. 8.2 .................................. 8.3.1 ............................... 8.3.2 ............................... 8.4 .................................. BTP 8–2 ......................... BTP 8–3 ......................... BTP 8–6 ......................... 9.1.3 ............................... 9.2.1 ............................... 9.2.2 ............................... 9.2.4 ............................... 9.2.5 ............................... 9.2.6 ............................... 9.3.2 ............................... 9.3.3 ............................... 9.4.1 ............................... 9.4.2 ............................... 9.4.3 ............................... 9.4.4 ............................... 9.5.2 ............................... 9.5.3 ............................... 10.2 ................................ 10.2.3 ............................. 10.3 ................................ 10.3.6 ............................. 10.4.1 ............................. 10.4.2 ............................. 10.4.3 ............................. 10.4.4 ............................. 10.4.5 ............................. 10.4.6 ............................. 10.4.7 ............................. 11.1 ................................ 11.2 ................................ 11.3 ................................ 11.4 ................................ 11.5 ................................ 11.6 ................................ Electric Power/Introduction ..................................................................................................................... Offsite Power System ............................................................................................................................. A C Power Systems (Onsite) .................................................................................................................. D C Power Systems (Onsite) .................................................................................................................. Station Blackout ...................................................................................................................................... Use of Diesel-Generator Sets for Peaking ............................................................................................. Stability of Offsite Power Systems .......................................................................................................... Adequacy of Station Electric Distribution System Voltages ................................................................... Spent Fuel Pool Cooling and Cleanup System ...................................................................................... Station Service Water System ................................................................................................................ Reactor Auxiliary Cooling Water Systems .............................................................................................. Potable and Sanitary Water Systems ..................................................................................................... Ultimate Heat Sink .................................................................................................................................. Condensate Storage Facilities ................................................................................................................ Process and Post Accident Sampling Systems ...................................................................................... Equipment and Floor Drainage System .................................................................................................. Control Room Area Ventilation System .................................................................................................. Spent Fuel Pool Area Ventilation System .............................................................................................. Reactor Service Building HVAC Systems .............................................................................................. Turbine Area Ventilation System ............................................................................................................ Communications Systems ....................................................................................................................... Lighting Systems ..................................................................................................................................... Turbine Generator ................................................................................................................................... Turbine Rotor Integrity ............................................................................................................................ Main Steam Supply System .................................................................................................................... Steam and Feedwater System Materials ................................................................................................ Main Condensers .................................................................................................................................... Main Condenser Evacuation System ...................................................................................................... Turbine Gland Sealing System ............................................................................................................... Turbine Bypass System .......................................................................................................................... Circulating Water System ....................................................................................................................... Condensate Cleanup System ................................................................................................................. Condensate and Feedwater System ...................................................................................................... Source Terms .......................................................................................................................................... Liquid Waste Management Systems ...................................................................................................... Gaseous Waste Management Systems ................................................................................................. Solid Waste Management Systems ........................................................................................................ Process and Effluent Radiological Monitoring Instrumentation and Sampling Systems ........................ Guidance on Instrumentation and Control Design Features for Process and Effluent Radiological Monitoring, and Area Radiation and Airborne Radioactivity Monitoring. Design Guidance for Solid Radioactive Waste Management Systems Installed in Light-Water -Cooled Nuclear Power Reactor Plants. Postulated Radioactive Releases Due to a Waste Gas System Leak or Failure .................................. Assuring that Occupational Radiation Exposures Are As Low As Is Reasonably Achievable .............. Radiation Sources ................................................................................................................................... Radiation Protection Design Features .................................................................................................... Operational Radiation Protection Program ............................................................................................. Initial Plant Test Program—Design Certification and New License Applicants ..................................... Structural and Systems Engineering—Inspections, Tests, Analyses, and Acceptance Criteria ............ Reactor Systems—Inspections, Tests, Analyses, and Acceptance Criteria .......................................... Instrumentation and Controls—Inspections, Tests, Analyses, and Acceptance Criteria ....................... Electrical Systems—Inspections, Tests, Analyses, and Acceptance Criteria ........................................ Plant Systems—Inspections, Tests, Analyses, and Acceptance Criteria ............................................... Radiation Protection—Inspections, Tests, Analyses, and Acceptance Criteria ..................................... 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 ............. ML12269A005 ML12269A006 ML12269A010 ML12269A011 ML12269A015 ML12269A016 ML12269A017 ML12269A018 ML12319A063 ML12319A068 ML12325A088 ML12319A091 ML12319A423 ML12270A276 ML12170A005 ML12319A437 ML12276A130 ML12272A229 ML12276A133 ML12221A117 ML12277A361 ML12319A516 ML12320A111 ML12272A247 ML12320A134 ML12272A004 ML12320A139 ML12320A146 ML12320A157 ML12320A161 ML12320A172 ML12272A242 ML12320A183 ML12222A292 ML12257A228 ML12257A227 ML12257A223 ML12258A115 ML13023A089 BTP 11–3 ....................... BTP 11–5 ....................... 12.1 ................................ 12.2 ................................ 12.3—12.4 ..................... 12.5 ................................ 14.2 ................................ 14.3.2 ............................. 14.3.4 ............................. 14.3.5 ............................. 14.3.6 ............................. 14.3.7 ............................. 14.3.8 ............................. 15.0 ................................ 15.0.2 ............................. 15.0.3 ............................. 15.1.5 ............................. 15.2.1–15.2.5 ................. mstockstill on DSK4VPTVN1PROD with NOTICES 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 ............................. VerDate Mar<15>2010 16:52 May 13, 2013 Jkt 229001 PO 00000 Frm 00080 Fmt 4703 Sfmt 4703 E:\FR\FM\14MYN1.SGM 14MYN1 ML12222A293 ML12222A294 ML12222A295 ML12222A296 ML12269A175 ML12257A224 ML12121A037 ML12272A243 ML12353A174 ML12325A091 ML12320A188 ML12320A195 ML12257A225 ML12275A026 ML12207A098 ML12257A226 ML12207A108 ML12319A584 ML12319A587 ML12250A248 ML12319A668 ML12319A585 ML12319A586 ML12240A005 ML12242A102 ML12261A399 ML12319A575 ML12250A318 28262 Federal Register / Vol. 78, No. 93 / Tuesday, May 14, 2013 / Notices Section Design-specific review standard title ADAMS No. 15.6.5 ............................. Loss of Coolant Accidents Resulting From Spectrum of Postulated Piping Breaks Within the Reactor Coolant Pressure Boundary. Anticipated Transients Without Scram .................................................................................................... Thermal Hydraulic Stability ..................................................................................................................... Technical Specifications .......................................................................................................................... ML12319A576 15.8 ................................ 15.9.A ............................. 16.0 ................................ Dated at Rockville, Maryland, this 6th day of May, 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. 2013–11394 Filed 5–13–13; 8:45 am] BILLING CODE 7590–01–P SECURITIES AND EXCHANGE COMMISSION [Release No. 34–69535; File No. SR–CBOE– 2013–043] Self-Regulatory Organizations; Chicago Board Options Exchange, Incorporated; Notice of Filing of a Proposed Rule Change Relating to Exchange Rule 9.21 May 8, 2013. Pursuant to Section 19(b)(1) of the Securities Exchange Act of 1934 (the ‘‘Act’’),1 and Rule 19b–4 thereunder,2 notice is hereby given that on April 25, 2013, Chicago Board Options Exchange, Incorporated (the ‘‘Exchange’’ or ‘‘CBOE’’) filed with the Securities and Exchange Commission (the ‘‘Commission’’) the proposed rule change as described in Items I, II, and III below, which Items have been substantially prepared by the Exchange. The Commission is publishing this notice to solicit comments on the proposed rule change from interested persons. mstockstill on DSK4VPTVN1PROD with NOTICES I. Self-Regulatory Organization’s Statement of the Terms of Substance of the Proposed Rule Change The Exchange proposes to update Exchange Rule 9.21, ‘‘Options Communications.’’ The text of the proposed rule change is provided below. (additions are italicized; deletions are [bracketed]) * * * * * Chicago Board Options Exchange, Incorporated Rules * * 1 15 2 17 * * * U.S.C. 78s(b)(1). CFR 240.19b–4. VerDate Mar<15>2010 16:52 May 13, 2013 Jkt 229001 Rule 9.21. Options Communications (a) Definitions. For purposes of this Rule and any interpretation thereof, ‘‘options communications’’ consist of: (i) [Advertisements. The term ‘‘advertisements’’ shall include any material concerning options, other than an independently prepared reprint and institutional sales material, that is published, or used in any electronic or other public media, including any Web site, newspaper, magazine or other periodical, radio, television, telephone or tape recording, video tape display, motion picture, billboards, signs or telephone directories (other than routine listings). (ii) Sales Literature. The term ‘‘sales literature’’ shall include any written or electronic communication concerning options other than an advertisement, independently prepared reprint, institutional sales material and correspondence, that is generally available to customers or the public, including circulars, research reports, performance reports or summaries, worksheets, form letters, telemarketing scripts, seminar texts, reprints (that are not independently prepared reprints) or excerpts of any other advertisement, sales literature or published article and press release concerning a Trading Permit Holder’s products or services. (iii)] Correspondence. The term ‘‘correspondence’’ shall include any written [letter,] (including electronic) [mail message or market letter] communication distributed or made available [by a Trading Permit Holder] to[: (A) one of more of its existing retail customers; and (B)] 25 or fewer [than 25 prospective] retail customers within any 30 calendar-day period. [(iv)] (ii) Institutional Communication [Sales Material]. The term ‘‘institutional communication [sales material]’’ shall include any written (including electronic) communication concerning options that is distributed or made available only to institutional investors, but does not include a Trading Permit Holder’s internal communications. The term institutional investor shall mean any qualified investor as defined in Section 3(a)(54) of the Securities Exchange Act of 1934. (iii) Retail Communication. The term ‘‘retail communication’’ means any PO 00000 Frm 00081 Fmt 4703 Sfmt 4703 ML12319A577 ML12261A042 ML12270A277 written (including electronic) communication that is distributed or made available to more than 25 retail investors within any 30 calendar-day period. [(v) Public Appearances. The term ‘‘public appearance’’ shall include any participation in a seminar, forum (including an interactive electronic forum), radio, television or print media interview, or other public speaking activity, or the writing of a print media article, concerning options. (vi) Independently Prepared Reprints. The term ‘‘independently prepared reprints’’ shall include any reprint or excerpt of an article issued by a publisher concerning options, provided that: the publisher is not an affiliate of the Trading Permit Holder using the reprint or any underwriter or issuer of a security mentioned in the reprint or excerpt that the Trading Permit Holder is promoting; neither the Trading Permit Holder using the reprint or excerpt nor any underwriter or issuer of a security mentioned in the reprint or excerpt has commissioned the reprint or excerpted article; and the Trading Permit Holder using the reprint or excerpt has not materially altered its contents except as necessary to make the reprint or excerpt consistent with applicable regulatory standards or to correct factual errors.] (b) Approval by Registered Options Principal. (i) All retail communications [advertisements, sales literature] (except completed worksheets) [and independently prepared reprints] issued by a Trading Permit Holder or TPH organization pertaining to options shall be approved in advance by a Registered Options Principal designated by the Trading Permit Holder or TPH organization’s written supervisory procedures. (ii) Correspondence need not be approved by a Registered Options Principal prior to use[, unless such correspondence is distributed to 25 or more existing retail customers within any 30 calendar-day period and makes any financial or investment recommendation or otherwise promotes a product or service of the Trading Permit Holder]. All correspondence is subject to the supervision and review requirements of Rule 9.8. E:\FR\FM\14MYN1.SGM 14MYN1

Agencies

[Federal Register Volume 78, Number 93 (Tuesday, May 14, 2013)]
[Notices]
[Pages 28258-28262]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2013-11394]


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

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; request for comment.

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

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is soliciting 
public comment on the Design-Specific Review Standard (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.

DATES: Submit comments by August 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 comment 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: 301-492-
3668; email: Carol.Gallagher@nrc.gov. For technical questions, contact 
the 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: TWB-05-B01M, U.S. Nuclear Regulatory Commission, Washington, 
DC 20555-0001.
     Fax comments to: RADB at 301-492-3446.

[[Page 28259]]

    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: Ms. Yanely Malave, Office of New 
Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001; telephone: 301-415-1519 or email at 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 information related to this document, which the NRC possesses 
and is publicly-available, 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 
mPower\TM\ DSRS Scope and Safety Review Matrix is available in ADAMS 
under Accession No. ML13088A252.
     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 Design-Specific Review Standard. This DSRS for the mPower\TM\ 
design is the result of the implementation of the Commission's 
direction.

B. Design-Specific Review Standard (DSRS) for the mPower\TM\ Design

    As part of the mPower\TM\ Design-Specific Review Plan, the Office 
of New Reactors has issued the mPower\TM\ Design-Specific Review 
Standard Scope and Safety Review Matrix 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 10 CFR Part 52. 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.
    The NRC staff is issuing this notice to solicit public comment on 
the mPower\TM\ DSRS Scope and Safety Review Matrix (Matrix), and the 
individual mPower\TM\-specific DSRS sections. Specifically, we request 
comment on the sufficiency of the proposed mPower\TM\ review scope 
encompassed by the Matrix, and comment on technical content of the 
individual mPower\TM\ DSRS sections identified in the table below that 
were revised or developed to incorporate design-specific review 
guidance based on features of the mPower\TM\ reactor design. We are 
not, however, soliciting detailed technical comments on NUREG-0800 
Standard Review Plan sections that are designated with the 
applicability ``A) Use SRP Section as-is . . .'' in the Matrix unless 
their adequacy for review of the mPower\TM\ design is in question.

------------------------------------------------------------------------
                                  Design-specific review
             Section                  standard title         ADAMS No.
------------------------------------------------------------------------
Matrix..........................  mPower\TM\ DSRS Scope      ML13088A252
                                   and Safety Review
                                   Matrix.
2.4.0...........................  Hydrology Review......     ML12355A691
2.4.1...........................  Hydrologic Description     ML12221A023
2.4.2...........................  Floods................     ML12221A024
2.4.3...........................  Probable Maximum Flood     ML12221A025
                                   (PMF) on Streams and
                                   Rivers.
2.4.4...........................  Potential Dam Failures     ML12221A026
2.4.5...........................  Probable Maximum Surge     ML12221A027
                                   and Seiche Flooding.
2.4.6...........................  Probable Maximum           ML12221A028
                                   Tsunami Flooding.
2.4.7...........................  Ice Effects...........     ML12221A017
2.4.9...........................  Channel Diversions....     ML12221A018
2.4.10..........................  Flooding Protection        ML12221A019
                                   Requirements.
2.4.12..........................  Groundwater...........     ML12221A020

[[Page 28260]]

 
2.4.13..........................  Accidental Releases of     ML12221A021
                                   Radioactive Liquid
                                   Effluents in Ground
                                   and Surface Waters.
2.4.14..........................  Technical                  ML12221A022
                                   Specifications and
                                   Emergency Operation
                                   Requirements.
3.2.1...........................  Seismic Classification     ML12272A013
3.2.2...........................  System Quality Group       ML12272A015
                                   Classification.
3.3.1...........................  Severe Wind Loading...     ML12324A156
3.3.2...........................  Extreme Wind Loads         ML12324A166
                                   (Tornado and
                                   Hurricane Loads).
3.4.1...........................  Internal Flood             ML12312A148
                                   Protection for Onsite
                                   Equipment Failure.
3.4.2...........................  Protection of              ML12324A190
                                   Structures Against
                                   Flood From External
                                   Sources.
3.5.1.1.........................  Internally Generated       ML12313A158
                                   Missiles (Outside
                                   Containment).
3.5.1.2.........................  Internally Generated       ML12313A396
                                   Missiles (Inside
                                   Containment).
3.5.1.3.........................  Turbine Missiles......     ML12272A209
3.5.1.4.........................  Missiles Generated by      ML12313A399
                                   Extreme Winds.
3.5.1.5.........................  Site Proximity             ML12318A151
                                   Missiles (Except
                                   Aircraft).
3.5.1.6.........................  Aircraft Hazards......     ML12318A198
3.5.2...........................  Structures, Systems,       ML12313A457
                                   and Components To Be
                                   Protected From
                                   Externally Generated
                                   Missiles.
3.5.3...........................  Barrier Design             ML12222A003
                                   Procedures.
3.6.2...........................  Determination of           ML12230A013
                                   Rupture Locations and
                                   Dynamic Effects
                                   Associated with the
                                   Postulated Rupture of
                                   Piping.
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.
3.8.4...........................  Other Seismic Category     ML13099A316
                                   I Structures.
3.8.5...........................  Foundations...........     ML13099A319
3.9.1...........................  Special Topics for         ML12272A018
                                   Mechanical Components.
3.9.4...........................  Control Rod Drive          ML12272A020
                                   Systems.
3.9.5...........................  Reactor Pressure           ML12272A077
                                   Vessel Internals.
3.9.6...........................  Functional Design,         ML12272A217
                                   Qualification, and
                                   Inservice Testing
                                   Programs for Pumps,
                                   Valves, and Dynamic
                                   Restraints.
3.11............................  Environmental              ML12277A018
                                   Qualification of
                                   Mechanical and
                                   Electrical Equipment.
3.13............................  Threaded Fasteners--       ML12272A214
                                   ASME Code Class 1, 2,
                                   and 3.
BTP 3-4.........................  Postulated Rupture         ML12272A102
                                   Locations in Fluid
                                   System Piping Inside
                                   and Outside
                                   Containment.
4.2.............................  Fuel System Design....     ML12235A168
4.3.............................  Nuclear Design........     ML12353A188
4.4.............................  Thermal and Hydraulic      ML12319A580
                                   Design.
4.5.1...........................  Control Rod Drive          ML12326A740
                                   Structural Materials.
4.5.2...........................  Reactor Internal and       ML12272A006
                                   Core Support
                                   Structure Materials.
4.6.............................  Functional Design of       ML12353A182
                                   Control Rod Drive
                                   System.
5.2.1.1.........................  Compliance With the        ML12272A091
                                   Codes and Standards
                                   Rule, 10 CFR 50.55a.
5.2.1.2.........................  Applicable Code Cases.     ML12272A096
5.2.3...........................  Reactor Coolant            ML12272A007
                                   Pressure Boundary
                                   Materials.
5.2.5...........................  Reactor Coolant            ML12313A468
                                   Pressure Boundary
                                   Leakage Detection.
5.3.1...........................  Reactor Vessel             ML12272A008
                                   Materials.
5.3.2...........................  Pressure-Temperature       ML12272A009
                                   Limits, Upper-shelf
                                   Energy, and
                                   Pressurized Thermal
                                   Shock.
5.3.3...........................  Reactor Vessel             ML12272A010
                                   Integrity.
5.4.2.1.........................  Steam Generator            ML12272A244
                                   Materials.
5.4.2.2.........................  Steam Generator            ML12272A245
                                   Program.
5.4.7...........................  Residual Heat Removal      ML12319A582
                                   (RHR) System.
BTP 5-4.........................  Design Requirements of     ML12275A020
                                   the Residual Heat
                                   Removal System.
6.1.1...........................  Engineered Safety          ML12276A107
                                   Features Materials.
6.1.2...........................  Protective Coating         ML12272A246
                                   Systems (Paints)--
                                   Organic Materials.
6.2.1...........................  Containment Functional     ML12276A117
                                   Design.
6.2.1.1.........................  mPower iPWR                ML12227A377
                                   Containment.
6.2.1.2.........................  Subcompartment             ML12230A014
                                   Analysis.
6.2.1.3.........................  Mass and Energy            ML12230A034
                                   Release Analysis for
                                   Postulated Loss of
                                   Coolant Accidents.
6.2.1.4.........................  Mass and Energy            ML12230A037
                                   Release Analysis for
                                   Postulated Secondary
                                   System Pipe Ruptures.
6.2.2...........................  Containment Heat           ML12276A118
                                   Removal Systems.
6.2.4...........................  Containment Isolation      ML12276A120
                                   System.
6.2.5...........................  Combustible Gas            ML12276A124
                                   Control in
                                   Containment.
6.2.6...........................  Containment Leakage        ML12276A127
                                   Testing.
6.2.7...........................  Fracture Prevention of     ML12278A103
                                   Containment Pressure
                                   Boundary.
6.4.............................  Control Room               ML12272A225
                                   Habitability System.
6.6.............................  Inservice Inspection       ML12284A064
                                   and Testing of Class
                                   2 and 3 Components.
BTP 6-1.........................  PH for Emergency           ML12222A198
                                   Coolant Water for
                                   Pressurized Water
                                   Reactors.
BTP 6-2.........................  Minimum Containment        ML12227A380
                                   Pressure Model for
                                   PWR ECCS Performance
                                   Evaluation.
BTP 6-4.........................  Containment Purging        ML12227A384
                                   During Normal Plant
                                   Operations.
7.0 (DSRS)......................  Instrumentation and        ML12314A197
                                   Controls--Introductio
                                   n and Overview of
                                   Review Process.
7.1 (DSRS)......................  Instrumentation and        ML12313A479
                                   Controls--Fundamental
                                   Design Principles.
7.2 (DSRS)......................  Instrumentation and        ML12314A201
                                   Controls--System
                                   Characteristics.
7.0 APP A (DSRS)................  Instrumentation and        ML12318A200
                                   Controls--Hazard
                                   Analysis.
7.0 APP B (DSRS)................  Instrumentation and        ML12318A201
                                   Controls--System
                                   Architecture.
7.0 APP C (DSRS)................  Instrumentation and        ML12318A204
                                   Controls--Simplicity.
7.0 APP D (DSRS)................  Instrumentation and        ML12318A205
                                   Controls--References.

[[Page 28261]]

 
8.1.............................  Electric Power/            ML12269A005
                                   Introduction.
8.2.............................  Offsite Power System..     ML12269A006
8.3.1...........................  A C Power Systems          ML12269A010
                                   (Onsite).
8.3.2...........................  D C Power Systems          ML12269A011
                                   (Onsite).
8.4.............................  Station Blackout......     ML12269A015
BTP 8-2.........................  Use of Diesel-             ML12269A016
                                   Generator Sets for
                                   Peaking.
BTP 8-3.........................  Stability of Offsite       ML12269A017
                                   Power Systems.
BTP 8-6.........................  Adequacy of Station        ML12269A018
                                   Electric Distribution
                                   System Voltages.
9.1.3...........................  Spent Fuel Pool            ML12319A063
                                   Cooling and Cleanup
                                   System.
9.2.1...........................  Station Service Water      ML12319A068
                                   System.
9.2.2...........................  Reactor Auxiliary          ML12325A088
                                   Cooling Water Systems.
9.2.4...........................  Potable and Sanitary       ML12319A091
                                   Water Systems.
9.2.5...........................  Ultimate Heat Sink....     ML12319A423
9.2.6...........................  Condensate Storage         ML12270A276
                                   Facilities.
9.3.2...........................  Process and Post           ML12170A005
                                   Accident Sampling
                                   Systems.
9.3.3...........................  Equipment and Floor        ML12319A437
                                   Drainage System.
9.4.1...........................  Control Room Area          ML12276A130
                                   Ventilation System.
9.4.2...........................  Spent Fuel Pool Area       ML12272A229
                                   Ventilation System.
9.4.3...........................  Reactor Service            ML12276A133
                                   Building HVAC Systems.
9.4.4...........................  Turbine Area               ML12221A117
                                   Ventilation System.
9.5.2...........................  Communications Systems     ML12277A361
9.5.3...........................  Lighting Systems......     ML12319A516
10.2............................  Turbine Generator.....     ML12320A111
10.2.3..........................  Turbine Rotor              ML12272A247
                                   Integrity.
10.3............................  Main Steam Supply          ML12320A134
                                   System.
10.3.6..........................  Steam and Feedwater        ML12272A004
                                   System Materials.
10.4.1..........................  Main Condensers.......     ML12320A139
10.4.2..........................  Main Condenser             ML12320A146
                                   Evacuation System.
10.4.3..........................  Turbine Gland Sealing      ML12320A157
                                   System.
10.4.4..........................  Turbine Bypass System.     ML12320A161
10.4.5..........................  Circulating Water          ML12320A172
                                   System.
10.4.6..........................  Condensate Cleanup         ML12272A242
                                   System.
10.4.7..........................  Condensate and             ML12320A183
                                   Feedwater System.
11.1............................  Source Terms..........     ML12222A292
11.2............................  Liquid Waste               ML12257A228
                                   Management Systems.
11.3............................  Gaseous Waste              ML12257A227
                                   Management Systems.
11.4............................  Solid Waste Management     ML12257A223
                                   Systems.
11.5............................  Process and Effluent       ML12258A115
                                   Radiological
                                   Monitoring
                                   Instrumentation and
                                   Sampling Systems.
11.6............................  Guidance on                ML13023A089
                                   Instrumentation and
                                   Control Design
                                   Features for Process
                                   and Effluent
                                   Radiological
                                   Monitoring, and Area
                                   Radiation and
                                   Airborne
                                   Radioactivity
                                   Monitoring.
BTP 11-3........................  Design Guidance for        ML12222A293
                                   Solid Radioactive
                                   Waste Management
                                   Systems Installed in
                                   Light-Water -Cooled
                                   Nuclear Power Reactor
                                   Plants.
BTP 11-5........................  Postulated Radioactive     ML12222A294
                                   Releases Due to a
                                   Waste Gas System Leak
                                   or Failure.
12.1............................  Assuring that              ML12222A295
                                   Occupational
                                   Radiation Exposures
                                   Are As Low As Is
                                   Reasonably Achievable.
12.2............................  Radiation Sources.....     ML12222A296
12.3--12.4......................  Radiation Protection       ML12269A175
                                   Design Features.
12.5............................  Operational Radiation      ML12257A224
                                   Protection Program.
14.2............................  Initial Plant Test         ML12121A037
                                   Program--Design
                                   Certification and New
                                   License Applicants.
14.3.2..........................  Structural and Systems     ML12272A243
                                   Engineering--Inspecti
                                   ons, Tests, Analyses,
                                   and Acceptance
                                   Criteria.
14.3.4..........................  Reactor Systems--          ML12353A174
                                   Inspections, Tests,
                                   Analyses, and
                                   Acceptance Criteria.
14.3.5..........................  Instrumentation and        ML12325A091
                                   Controls--Inspections
                                   , Tests, Analyses,
                                   and Acceptance
                                   Criteria.
14.3.6..........................  Electrical Systems--       ML12320A188
                                   Inspections, Tests,
                                   Analyses, and
                                   Acceptance Criteria.
14.3.7..........................  Plant Systems--            ML12320A195
                                   Inspections, Tests,
                                   Analyses, and
                                   Acceptance Criteria.
14.3.8..........................  Radiation Protection--     ML12257A225
                                   Inspections, Tests,
                                   Analyses, and
                                   Acceptance Criteria.
15.0............................   Introduction--Transie     ML12275A026
                                   nt 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.

[[Page 28262]]

 
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.
15.9.A..........................  Thermal Hydraulic          ML12261A042
                                   Stability.
16.0............................  Technical                  ML12270A277
                                   Specifications.
------------------------------------------------------------------------


    Dated at Rockville, Maryland, this 6th day of May, 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. 2013-11394 Filed 5-13-13; 8:45 am]
BILLING CODE 7590-01-P