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: https://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 https://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 https://www.regulations.gov and search for Docket ID NRC–2013–0089. • NRC’s Agencywide Documents Access and Management System (ADAMS): You may access publiclyavailable documents online in the NRC Library at https://www.nrc.gov/readingrm/adams.html. To begin the search, select ‘‘ADAMS Public Documents’’ and then select ‘‘Begin Web-based ADAMS Search.’’ For problems with ADAMS, please contact the NRC’s Public Document Room (PDR) reference staff at 1–800–397–4209, 301–415–4737, or by email to pdr.resource@nrc.gov. The ADAMS accession number for each document referenced in this notice (if that document is available in ADAMS) is provided the first time that a document is referenced and also in the table included in this notice. The 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 https:// www.regulations.gov as well as entering the comment submissions into ADAMS. The NRC does not routinely edit comment submissions to remove identifying or contact information. If you are requesting or aggregating comments from other persons for submission to the NRC, then you should inform those persons not to include identifying or contact information that they do not want to be publicly disclosed in their comment submission. Your request should state that the NRC does not routinely edit comment submissions to remove such information before making the comment submissions available to the public or entering the comment submissions into ADAMS. II. Further Information A. Background In 2010, the Commission provided direction to the staff on the preparation for, and review of, small modular reactor (SMR) applications, with a nearterm focus on integral pressurized water reactor (iPWR) designs. The Commission directed the staff to more fully integrate the use of risk insights into pre-application activities and the review of applications and, consistent with regulatory requirements and Commission policy statements, to align the review focus and resources to risksignificant structures, systems, and components and other aspects of the design that contribute most to safety in order to enhance the effectiveness and 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

NUCLEAR REGULATORY COMMISSION

[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 https://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 https://www.regulations.gov and search for Docket ID NRC-2013-0089.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may access publicly-available documents online in the NRC
Library at https://www.nrc.gov/reading-rm/adams.html. To begin the
search, select ``ADAMS Public Documents'' and then select ``Begin Web-
based ADAMS Search.'' For problems with ADAMS, please contact the NRC's
Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-
4737, or by email to pdr.resource@nrc.gov. The ADAMS accession number
for each document referenced in this notice (if that document is
available in ADAMS) is provided the first time that a document is
referenced and also in the table included in this notice. The
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 https://www.regulations.gov as well as entering the comment submissions into
ADAMS. The NRC does not routinely edit comment submissions to remove
identifying or contact information.
If you are requesting or aggregating comments from other persons
for submission to the NRC, then you should inform those persons not to
include identifying or contact information that they do not want to be
publicly disclosed in their comment submission. Your request should
state that the NRC does not routinely edit comment submissions to
remove such information before making the comment submissions available
to the public or entering the comment submissions into ADAMS.

II. Further Information

A. Background

In 2010, the Commission provided direction to the staff on the
preparation for, and review of, small modular reactor (SMR)
applications, with a near-term focus on integral pressurized water
reactor (iPWR) designs. The Commission directed the staff to more fully
integrate the use of risk insights into pre-application activities and
the review of applications and, consistent with regulatory requirements
and Commission policy statements, to align the review focus and
resources to risk-significant structures, systems, and components and
other aspects of the design that contribute most to safety in order to
enhance the effectiveness and efficiency of the review process. The
Commission directed the staff to develop a design-specific, risk-
informed review plan for each SMR design to address pre-application and
application review activities. An important part of this review plan is
the 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

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