80 FR 37312 - NuScale Power, LLC, Design-Specific Review Standard and Safety Review Matrix
NUCLEAR REGULATORY COMMISSION Federal Register Volume 80, Issue 125 (June 30, 2015)
Federal Register Volume 80, Issue 125 (June 30, 2015)
| Page Range | 37312-37314 | |
| FR Document | 2015-16034 |
[Federal Register Volume 80, Number 125 (Tuesday, June 30, 2015)] [Notices] [Pages 37312-37314] From the Federal Register Online [www.thefederalregister.org] [FR Doc No: 2015-16034] [[Page 37312]] ======================================================================= ----------------------------------------------------------------------- NUCLEAR REGULATORY COMMISSION [NRC-2015-0160] NuScale Power, LLC, Design-Specific Review Standard and Safety Review Matrix AGENCY: Nuclear Regulatory Commission. ACTION: Design-specific review standard; request for comment. ----------------------------------------------------------------------- SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on the Design-Specific Review Standard (DSRS) and Safety Review Matrix for the NuScale Power, LLC, design (NuScale DSRS Scope and Safety Review Matrix). The purpose of the NuScale DSRS is to provide guidance to NRC staff in performing safety reviews where existing NUREG-0800, ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition,'' Standard Review Plans (SRP) have been modified by the staff specifically for the NuScale design, or do not address unique features of the NuScale design. The DSRS also allows NRC staff to more fully integrate the use of design-specific risk insights into the review of the NuScale design certification application (DC) or an early site permit (ESP) or combined license (COL) application that references the NuScale design. DATES: Submit comments by August 31, 2015. Comments received after this date will be considered, if it is practical to do so, but the NRC is able to ensure consideration only for comments received on or before this date. ADDRESSES: You may submit comments by any of the following methods (unless this document describes a different method for submitting comments on a specific subject):Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2015-0160. Address questions about NRC dockets to Carol Gallagher; telephone: 301-415- 3463; email: [email protected]. For technical questions, contact the individual 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: OWFN-12-H08, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. For additional direction on obtaining information and submitting comments, see ``Obtaining Information and Submitting Comments'' in the SUPPLEMENTARY INFORMATION section of this document. FOR FURTHER INFORMATION CONTACT: Jenny Gallo, Office of New Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-7367; email: [email protected]. SUPPLEMENTARY INFORMATION: I. Obtaining Information and Submitting Comments A. Obtaining Information Please refer to Docket ID NRC-2015-0160 when contacting the NRC about the availability of information regarding this document. You may obtain publicly-available information related to this action by any of the following methods: Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2015-0160. NRC's Agencywide Documents Access and Management System (ADAMS): You may obtain publicly-available documents online in the ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS, please contact the NRC's Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-4737, or by email to [email protected]. The ADAMS accession number for each document referenced (if it is available in ADAMS) is provided the first time that it is mentioned in the SUPPLEMENTARY INFORMATION section. The NuScale DSRS Scope and Safety Review Matrix is available in ADAMS under Accession No. ML15156B063. 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-2015-0160 in your comment submission. 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 will post all comment submissions at http://www.regulations.gov as well as enter 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 into ADAMS. II. Further Information A. Background In the Staff Requirements Memorandum (SRM) COMGBJ-10-0004/COMGEA- 10-0001, ``Use of Risk Insights to Enhance the Safety Focus of Small Modular Reactor Reviews,'' dated August 31, 2010 (ADAMS Accession No. ML102510405), the Commission provided direction to the NRC staff on the preparation for, and review of, small modular reactor (SMR) applications, with a near-term focus on integral pressurized-water reactor designs. The Commission directed the NRC 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 NRC staff to develop a design-specific, risk- informed review plan for each SMR design to address pre-application and application review activities. An important part of this review plan is the DSRS. The DSRS for the NuScale design is the result of the implementation of the Commission's direction. B. DSRS for the NuScale Design The NuScale DSRS reflects current NRC staff safety review methods and practices which integrate risk insights and, where appropriate, lessons learned from the NRC's reviews of DC and COL applications completed since the last revision of the NUREG-0800, SRP Introduction, Part 2, ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: Light-Water Small Modular Reactor Edition,'' January 2014 (ADAMS Accession No. ML13207A315). The NuScale DSRS Scope and Safety Matrix provides a complete list of SRP sections and identifies which SRP sections will be used for DC, COL, or ESP reviews concerning the NuScale design; which SRP sections are not applicable to the [[Page 37313]] NuScale design; and which new DSRS sections are design-specific to NuScale. The NuScale DSRS Scope and Safety Review Matrix is available in ADAMS under Accession No. ML15156B063. The NRC staff is soliciting public comment on the NuScale DSRS Scope and Safety Review Matrix and the individual NuScale-specific DSRS sections referenced in the table below. Specifically, the NRC requests comment on the sufficiency of the scope of the proposed NuScale review, as encompassed by the Safety Review Matrix, and on the technical content of the individual NuScale-specific DSRS sections identified in the table below. These sections were revised from the relative SRP sections or developed to incorporate design-specific review guidance based on features of the NuScale design. The NRC is not soliciting general comments on NUREG-0800 sections that are designated with the applicability ``A) Use SRP Section'' in the Safety Review Matrix, but specific comments on the adequacy of these NUREG-0800 sections for use in the review of the NuScale design certification application will be considered. ---------------------------------------------------------------------------------------------------------------- Section Design-specific review standard title ADAMS Accession No. ---------------------------------------------------------------------------------------------------------------- Matrix........................... NuScale Power, LLC DSRS Scope and Safety ML15156B063 Review Matrix. 3.11............................. Environmental Qualification of Mechanical ML15131A247 and Electrical Equipment. 3.13............................. Threaded Fasteners--ASME Code Class 1, 2, ML15084A277 and 3. 3.3.1............................ Offsite Power System....................... ML15071A259 3.3.2............................ Tornado Loads.............................. ML15071A267 3.4.1............................ Internal Flood Protection for Onsite ML15139A112 Equipment Failures. 3.4.2............................ Analysis Procedures........................ ML15071A324 3.5.1.1.......................... Internally Generated Missiles (Outside ML15139A081 Containment). 3.5.1.2.......................... Internally Generated Missiles (Inside ML15139A096 Containment). 3.5.1.3.......................... Turbine Missiles........................... ML15070A248 3.5.1.4.......................... Missiles Generated by Tornadoes and Extreme ML15139A121 Winds. 3.5.2............................ Structures, Systems, and Components to be ML15139A102 Protected from Externally-Generated Missiles. 3.5.3............................ Barrier Design Procedures.................. ML15071A273 3.7.1............................ Seismic Design Parameters.................. ML15084A279 3.7.2............................ Seismic System Analysis.................... ML15084A177 3.7.3............................ Seismic Subsystem Analysis................. ML15131A340 3.8.2............................ Steel Containment.......................... ML15131A373 3.8.4............................ Other Seismic Category I Structures........ ML15118A151 3.8.5............................ Foundations................................ ML15132A186 4.2.............................. Fuel System Design......................... ML15132A517 4.3.............................. Nuclear Design............................. ML15125A374 4.4.............................. Thermal and Hydraulic Design............... ML15131A427 4.5.2............................ Reactor Internal and Core Support Structure ML15070A325 Materials. 4.6.............................. Functional Design of Control Rod Drive ML15119A111 System. 5.2.2............................ Overpressure Protection.................... ML15118A931 5.2.4............................ Reactor Coolant Pressure Boundary Inservice ML15125A305 Inspection and Testing. 5.2.5............................ Reactor Coolant Pressure Boundary Leakage ML15132A194 Detection. 5.3.1............................ Reactor Vessel Materials................... ML15070A457 5.3.2............................ Pressure-Temperature Limits, ML15070A468 Upper[dash]Shelf Energy, and Pressurized Thermal Shock. 5.3.3............................ Reactor Vessel Integrity................... ML15070A462 5.4.............................. Rx Coolant System Component and Subsystem ML15126A156 Design. 5.4.2.1.......................... Steam Generator Materials.................. ML15131A376 5.4.2.2.......................... Steam Generator Program.................... ML15070A562 5.4.7............................ Residual Heat Removal (RHR) System......... ML15131A360 5-4 BTP.......................... Design Requirements of the RHR System...... ML15132A524 6.1.1............................ Engineered Safety Features Materials....... ML15070A567 6.1.2............................ Protective Coating Systems (Paints)-- ML15071A372 Organic Materials. 6-1 BTP.......................... pH for Emergency Coolant Water for PWRs.... ML15125A369 6.2.1............................ Containment Functional Design.............. ML15118A922 6.2.1.1.A........................ PWR Dry Containments, Including Sub- ML15118A264 atmospheric Containments. 6.2.1.3.......................... Mass and Energy Release Analysis for ML15112A134 Postulated Loss-of-Coolant Accidents (LOCAs). 6.2.1.4.......................... Mass and Energy Release Analysis for ML15118A293 Postulated Secondary System Pipe Ruptures. 6.2.2............................ Containment Heat Removal Systems........... ML15131A341 6.2.4............................ Containment Isolation System............... ML15119A087 6.2.5............................ Combustible Gas Control in Containment..... ML15119A090 6.2.6............................ Containment Leakage Testing................ ML15119A084 6.2.7............................ Fracture Prevention of Containment Pressure ML15112A517 Boundary. 6.3.............................. Emergency Core Cooling System.............. ML15125A322 6.6.............................. Inservice Inspection and Testing of Class 2 ML15127A136 and 3 Components. 7.0.............................. Instrumentation and Controls--Introduction ML15125A340 and Overview of Review Process. 7.0, A........................... Instrumentation and Controls--Hazard ML15132A583 Analysis. 7.0, B........................... Instrumentation and Controls--System ML15132A603 Architecture. 7.0, C........................... Instrumentation and Controls--Simplicity... ML15132A611 7.0, D........................... Instrumentation and Controls--References... ML15132A618 7.1.............................. I&C--Fundamental Design Principles......... ML15125A335 7.2.............................. Instrumentation and Controls--System ML15125A360 Characteristics. 8.1.............................. Electric Power--Introduction............... ML15146A269 8.2.............................. Offsite Power System....................... ML15125A425 8-2 BTP.......................... Use of Diesel-Generator Sets for Peaking... Ml15131A386 8.3.1............................ AC Power Systems (Onsite).................. ML15125A384 [[Page 37314]] 8.3.2............................ DC Power Systems (Onsite).................. ML15125A386 8-3 BTP.......................... Stability of Offsite Power Systems......... ML15125A390 8.4.............................. Station Blackout........................... ML15126A149 8-6 BTP.......................... Adequacy of Station Electric Distribution ML15131A461 System Voltages. 9.1.2............................ New and Spent Fuel Storage................. ML15125A307 9.1.3............................ Spent Fuel Pool Cooling and Cleanup System. ML15146A034 9.2.6............................ Condensate Storage Facilities.............. ML15131A245 9.3.2............................ Process and Post-Accident Sampling Systems. ML15131A298 9.3.4............................ Chemical and Volume Control System (PWR) ML15131A305 (Including Boron Recovery System). 9.3.6............................ Containment Evacuation and Flooding Systems ML15112A190 9.5.2............................ Communications Systems..................... ML15084A403 9.5.3............................ Lighting Systems........................... ML15112A148 10.2............................. Turbine Generator.......................... ML15126A086 10.2.3........................... Turbine Rotor Integrity.................... ML15127A046 10.3............................. Main Steam Supply System................... ML15131A329 10.4.1........................... Main Condensers............................ ML15127A049 10.4.2........................... Main Condenser Evacuation System........... ML15127A349 10.4.3........................... Turbine Gland Sealing System............... ML15126A477 10.4.4........................... Turbine Bypass System...................... ML15131A417 10.4.5........................... Circulating Water System................... ML15126A467 10.4.6........................... Condensate Cleanup System.................. ML15118A943 10.4.7........................... Condensate and Feedwater System............ ML15126A470 10.4.10.......................... Auxiliary Boiler System.................... ML15131A261 11.1............................. Source Terms............................... ML15112A526 11.2............................. Liquid Waste Management System............. ML15124A607 11.3............................. Gaseous Waste Management System............ ML15112A694 11.4............................. Solid Waste Management System.............. ML15119A057 11.5............................. Process and Effluent Radiological ML15118A609 Monitoring Instrumentation and Sampling Systems. 11.6............................. Guidance on I&C Design Features for Process ML15125A367 and Effluent Radiological Monitoring and Area Radiation and Airborne Radioactivity Monitoring. 12.2............................. Radiation Sources.......................... ML15070A194 12.3-12.4........................ Radiation Protection Design Features....... ML15070A204 12.5............................. Operational Radiation Protection Program... ML15070A210 14.2............................. Initial Plant Test Program--Design ML15084A407 Certification and New License Applicants. 14.3.2........................... Structural and Systems Engineering-- ML15084A411 Inspections, Tests, Analyses, and Acceptance Criteria. 14.3.4........................... Reactor Systems--Inspections, Tests, ML15125A294 Analyses, and Acceptance Criteria. 14.3.5........................... Instrumentation and Controls--Inspections, ML15127A383 Tests, Analyses, and Acceptance Criteria. 14.3.6........................... Electrical Systems--Inspections, Tests, ML15127A373 Analyses, and Acceptance Criteria. 14.3.7........................... Plant Systems--Inspections, Tests, ML15131A328 Analyses, and Acceptance Criteria. 15.0............................. Introduction--Transient and Accident ML15125A297 Analyses. 15.0.3........................... Design Basis Accidents Radiological ML15127A387 Consequence Analyses for Advanced Light Water Reactors. 15.1.1-15.1.4.................... Decrease in FW Temperature, Increase in FW ML15127A391 Flow, Increase in Steam Flow, and Inadvertent Opening of a Steam Generator Relief or Safety Valve. 15.1.5........................... Steam System Piping Failures Inside and ML15125A317 Outside of Containment (PWR). 15.1.6........................... Loss of Containment Vacuum................. ML15127A395 15.2.1-15.2.5.................... Loss of External Load; Turbine Trip; Loss ML15127A400 of Condenser Vacuum; Closure of Main Steam Isolation Valve (BWR); and Steam Pressure Regulator Failure (Closed). 15.2.6........................... Loss of Non-Emergency AC Power to the ML15125A292 Station Auxiliaries. 15.2.7........................... Loss of Normal Feedwater Flow.............. ML15125A293 15.2.8........................... Feedwater System Pipe Breaks Inside and ML15118A927 Outside Containment (PWR). 15.4.1........................... Uncontrolled Control Rod Assembly ML15118A482 Withdrawal from a Subcritical or Low Power Startup Condition. 15.4.2........................... Uncontrolled Control Rod Assembly ML15118A600 Withdrawal at Power. 15.4.3........................... Control Rod Misoperation (System ML15131A364 Malfunction or Operator Error). 15.4.6........................... Inadvertent Decrease in Boron Concentration ML15118A474 in the Reactor Coolant (PWR). 15.5.1-15.5.2.................... Chemical and Volume Control System ML15125A463 Malfunction that Increases Reactor Coolant Inventory. 15.6.5........................... LOCAs Resulting From Spectrum of Postulated ML15131A334 Piping Breaks Within the Reactor Coolant Pressure Boundary. 15.6.6........................... Inadvertent Opening of a PWR Pressurizer ML15125A467 Pressure Relief Valve. 15.9A............................ Thermal-hydraulic Stability................ ML15131A311 16.0............................. Technical Specifications................... ML15131A316 ---------------------------------------------------------------------------------------------------------------- Dated at Rockville, Maryland, this 23rd day of June 2015. For the Nuclear Regulatory Commission. Jenny M. Gallo, Project Manager, Small Modular Reactor Licensing Branch, Division of Advanced Reactors and Rulemaking, Office of New Reactors. [FR Doc. 2015-16034 Filed 6-29-15; 8:45 am] BILLING CODE 7590-01-P
![37312 Federal Register / Vol. 80, No. 125 / Tuesday, June 30, 2015 / Notices
NUCLEAR REGULATORY Submitting Comments’’ in the submission to the NRC, then you should
COMMISSION SUPPLEMENTARY INFORMATION section of inform those persons not to include
this document. identifying or contact information that
[NRC–2015–0160]
FOR FURTHER INFORMATION CONTACT: they do not want to be publicly
NuScale Power, LLC, Design-Specific Jenny Gallo, Office of New Reactors, disclosed in their comment submission.
Review Standard and Safety Review U.S. Nuclear Regulatory Commission, Your request should state that the NRC
Matrix Washington, DC 20555–0001; telephone: does not routinely edit comment
301–415–7367; email: NuScale-DSRS@ submissions to remove such information
AGENCY: Nuclear Regulatory nrc.gov. before making the comment
Commission. submissions available to the public or
SUPPLEMENTARY INFORMATION:
ACTION: Design-specific review standard; entering the comment into ADAMS.
request for comment. I. Obtaining Information and
Submitting Comments II. Further Information
SUMMARY: The U.S. Nuclear Regulatory A. Background
Commission (NRC) is soliciting public A. Obtaining Information
Please refer to Docket ID NRC–2015– In the Staff Requirements
comment on the Design-Specific Review
0160 when contacting the NRC about Memorandum (SRM) COMGBJ–10–
Standard (DSRS) and Safety Review
the availability of information regarding 0004/COMGEA–10–0001, ‘‘Use of Risk
Matrix for the NuScale Power, LLC,
this document. You may obtain Insights to Enhance the Safety Focus of
design (NuScale DSRS Scope and Safety
publicly-available information related to Small Modular Reactor Reviews,’’ dated
Review Matrix). The purpose of the
this action by any of the following August 31, 2010 (ADAMS Accession
NuScale DSRS is to provide guidance to
methods: No. ML102510405), the Commission
NRC staff in performing safety reviews
• Federal Rulemaking Web site: Go to provided direction to the NRC staff on
where existing NUREG–0800, ‘‘Standard
http://www.regulations.gov and search the preparation for, and review of, small
Review Plan for the Review of Safety
for Docket ID NRC–2015–0160. modular reactor (SMR) applications,
Analysis Reports for Nuclear Power
• NRC’s Agencywide Documents with a near-term focus on integral
Plants: LWR Edition,’’ Standard Review
Access and Management System pressurized-water reactor designs. The
Plans (SRP) have been modified by the
(ADAMS): You may obtain publicly- Commission directed the NRC staff to
staff specifically for the NuScale design,
available documents online in the more fully integrate the use of risk
or do not address unique features of the
ADAMS Public Documents collection at insights into pre-application activities
NuScale design. The DSRS also allows
http://www.nrc.gov/reading-rm/ and the review of applications and,
NRC staff to more fully integrate the use
adams.html. To begin the search, select consistent with regulatory requirements
of design-specific risk insights into the
‘‘ADAMS Public Documents’’ and then and Commission policy statements, to
review of the NuScale design
select ‘‘Begin Web-based ADAMS align the review focus and resources to
certification application (DC) or an early
Search.’’ For problems with ADAMS, risk-significant structures, systems, and
site permit (ESP) or combined license
please contact the NRC’s Public components and other aspects of the
(COL) application that references the
Document Room (PDR) reference staff at design that contribute most to safety in
NuScale design.
1–800–397–4209, 301–415–4737, or by order to enhance the effectiveness and
DATES: Submit comments by August 31, efficiency of the review process. The
2015. Comments received after this date email to pdr.resource@nrc.gov. The
ADAMS accession number for each Commission directed the NRC staff to
will be considered, if it is practical to do develop a design-specific, risk-informed
so, but the NRC is able to ensure document referenced (if it is available in
ADAMS) is provided the first time that review plan for each SMR design to
consideration only for comments address pre-application and application
received on or before this date. it is mentioned in the SUPPLEMENTARY
INFORMATION section. The NuScale DSRS review activities. An important part of
ADDRESSES: You may submit comments this review plan is the DSRS. The DSRS
Scope and Safety Review Matrix is
by any of the following methods (unless available in ADAMS under Accession for the NuScale design is the result of
this document describes a different No. ML15156B063. the implementation of the Commission’s
method for submitting comments on a • NRC’s PDR: You may examine and direction.
specific subject): purchase copies of public documents at
• Federal Rulemaking Web site: Go to B. DSRS for the NuScale Design
the NRC’s PDR, Room O1–F21, One
http://www.regulations.gov and search White Flint North, 11555 Rockville The NuScale DSRS reflects current
for Docket ID NRC–2015–0160. Address Pike, Rockville, Maryland 20852. NRC staff safety review methods and
questions about NRC dockets to Carol practices which integrate risk insights
Gallagher; telephone: 301–415–3463; B. Submitting Comments and, where appropriate, lessons learned
email: Carol.Gallagher@nrc.gov. For Please include Docket ID NRC–2015– from the NRC’s reviews of DC and COL
technical questions, contact the 0160 in your comment submission. applications completed since the last
individual listed in the FOR FURTHER The NRC cautions you not to include revision of the NUREG–0800, SRP
INFORMATION CONTACT section of this identifying or contact information that Introduction, Part 2, ‘‘Standard Review
document. you do not want to be publicly Plan for the Review of Safety Analysis
• Mail comments to: Cindy Bladey, disclosed in your comment submission. Reports for Nuclear Power Plants: Light-
Chief, Rules, Announcements, and The NRC will post all comment Water Small Modular Reactor Edition,’’
asabaliauskas on DSK5VPTVN1PROD with NOTICES
Directives Branch (RADB), Office of submissions at http:// January 2014 (ADAMS Accession No.
Administration, Mail Stop: OWFN–12– www.regulations.gov as well as enter the ML13207A315). The NuScale DSRS
H08, U.S. Nuclear Regulatory comment submissions into ADAMS. Scope and Safety Matrix provides a
Commission, Washington, DC 20555– The NRC does not routinely edit complete list of SRP sections and
0001. comment submissions to remove identifies which SRP sections will be
For additional direction on obtaining identifying or contact information. used for DC, COL, or ESP reviews
information and submitting comments, If you are requesting or aggregating concerning the NuScale design; which
see ‘‘Obtaining Information and comments from other persons for SRP sections are not applicable to the
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![37314 Federal Register / Vol. 80, No. 125 / Tuesday, June 30, 2015 / Notices
ADAMS
Section Design-specific review standard title Accession No.
8.3.2 ................... DC Power Systems (Onsite) ............................................................................................................................ ML15125A386
8–3 BTP ............ Stability of Offsite Power Systems ................................................................................................................... ML15125A390
8.4 ...................... Station Blackout ................................................................................................................................................ ML15126A149
8–6 BTP ............ Adequacy of Station Electric Distribution System Voltages ............................................................................. ML15131A461
9.1.2 ................... New and Spent Fuel Storage ........................................................................................................................... ML15125A307
9.1.3 ................... Spent Fuel Pool Cooling and Cleanup System ............................................................................................... ML15146A034
9.2.6 ................... Condensate Storage Facilities ......................................................................................................................... ML15131A245
9.3.2 ................... Process and Post-Accident Sampling Systems ............................................................................................... ML15131A298
9.3.4 ................... Chemical and Volume Control System (PWR) (Including Boron Recovery System) ...................................... ML15131A305
9.3.6 ................... Containment Evacuation and Flooding Systems ............................................................................................. ML15112A190
9.5.2 ................... Communications Systems ................................................................................................................................ ML15084A403
9.5.3 ................... Lighting Systems .............................................................................................................................................. ML15112A148
10.2 .................... Turbine Generator ............................................................................................................................................ ML15126A086
10.2.3 ................. Turbine Rotor Integrity ...................................................................................................................................... ML15127A046
10.3 .................... Main Steam Supply System ............................................................................................................................. ML15131A329
10.4.1 ................. Main Condensers ............................................................................................................................................. ML15127A049
10.4.2 ................. Main Condenser Evacuation System ............................................................................................................... ML15127A349
10.4.3 ................. Turbine Gland Sealing System ........................................................................................................................ ML15126A477
10.4.4 ................. Turbine Bypass System ................................................................................................................................... ML15131A417
10.4.5 ................. Circulating Water System ................................................................................................................................. ML15126A467
10.4.6 ................. Condensate Cleanup System ........................................................................................................................... ML15118A943
10.4.7 ................. Condensate and Feedwater System ................................................................................................................ ML15126A470
10.4.10 ............... Auxiliary Boiler System ..................................................................................................................................... ML15131A261
11.1 .................... Source Terms ................................................................................................................................................... ML15112A526
11.2 .................... Liquid Waste Management System ................................................................................................................. ML15124A607
11.3 .................... Gaseous Waste Management System ............................................................................................................. ML15112A694
11.4 .................... Solid Waste Management System ................................................................................................................... ML15119A057
11.5 .................... Process and Effluent Radiological Monitoring Instrumentation and Sampling Systems ................................. ML15118A609
11.6 .................... Guidance on I&C Design Features for Process and Effluent Radiological Monitoring and Area Radiation ML15125A367
and Airborne Radioactivity Monitoring.
12.2 .................... Radiation Sources ............................................................................................................................................ ML15070A194
12.3–12.4 ........... Radiation Protection Design Features ............................................................................................................. ML15070A204
12.5 .................... Operational Radiation Protection Program ...................................................................................................... ML15070A210
14.2 .................... Initial Plant Test Program—Design Certification and New License Applicants ............................................... ML15084A407
14.3.2 ................. Structural and Systems Engineering—Inspections, Tests, Analyses, and Acceptance Criteria ..................... ML15084A411
14.3.4 ................. Reactor Systems—Inspections, Tests, Analyses, and Acceptance Criteria .................................................... ML15125A294
14.3.5 ................. Instrumentation and Controls—Inspections, Tests, Analyses, and Acceptance Criteria ................................. ML15127A383
14.3.6 ................. Electrical Systems—Inspections, Tests, Analyses, and Acceptance Criteria .................................................. ML15127A373
14.3.7 ................. Plant Systems—Inspections, Tests, Analyses, and Acceptance Criteria ........................................................ ML15131A328
15.0 .................... Introduction—Transient and Accident Analyses .............................................................................................. ML15125A297
15.0.3 ................. Design Basis Accidents Radiological Consequence Analyses for Advanced Light Water Reactors .............. ML15127A387
15.1.1–15.1.4 ..... Decrease in FW Temperature, Increase in FW Flow, Increase in Steam Flow, and Inadvertent Opening of ML15127A391
a Steam Generator Relief or Safety Valve.
15.1.5 ................. Steam System Piping Failures Inside and Outside of Containment (PWR) .................................................... ML15125A317
15.1.6 ................. Loss of Containment Vacuum .......................................................................................................................... ML15127A395
15.2.1–15.2.5 ..... Loss of External Load; Turbine Trip; Loss of Condenser Vacuum; Closure of Main Steam Isolation Valve ML15127A400
(BWR); and Steam Pressure Regulator Failure (Closed).
15.2.6 ................. Loss of Non-Emergency AC Power to the Station Auxiliaries ......................................................................... ML15125A292
15.2.7 ................. Loss of Normal Feedwater Flow ...................................................................................................................... ML15125A293
15.2.8 ................. Feedwater System Pipe Breaks Inside and Outside Containment (PWR) ...................................................... ML15118A927
15.4.1 ................. Uncontrolled Control Rod Assembly Withdrawal from a Subcritical or Low Power Startup Condition ........... ML15118A482
15.4.2 ................. Uncontrolled Control Rod Assembly Withdrawal at Power .............................................................................. ML15118A600
15.4.3 ................. Control Rod Misoperation (System Malfunction or Operator Error) ................................................................. ML15131A364
15.4.6 ................. Inadvertent Decrease in Boron Concentration in the Reactor Coolant (PWR) ............................................... ML15118A474
15.5.1–15.5.2 ..... Chemical and Volume Control System Malfunction that Increases Reactor Coolant Inventory ..................... ML15125A463
15.6.5 ................. LOCAs Resulting From Spectrum of Postulated Piping Breaks Within the Reactor Coolant Pressure ML15131A334
Boundary.
15.6.6 ................. Inadvertent Opening of a PWR Pressurizer Pressure Relief Valve ................................................................ ML15125A467
15.9A ................. Thermal-hydraulic Stability ............................................................................................................................... ML15131A311
16.0 .................... Technical Specifications ................................................................................................................................... ML15131A316
Dated at Rockville, Maryland, this 23rd day For the Nuclear Regulatory Commission. NUCLEAR REGULATORY
asabaliauskas on DSK5VPTVN1PROD with NOTICES
of June 2015. Jenny M. Gallo, COMMISSION
Project Manager, Small Modular Reactor
Licensing Branch, Division of Advanced [NRC–2015–0001]
Reactors and Rulemaking, Office of New
Reactors. Sunshine Act Meeting Notice
[FR Doc. 2015–16034 Filed 6–29–15; 8:45 am]
BILLING CODE 7590–01–P DATE: June 29, July 6, 13, 20, 27, August
3, 2015.
VerDate Sep<11>2014 17:34 Jun 29, 2015 Jkt 235001 PO 00000 Frm 00096 Fmt 4703 Sfmt 4703 E:\FR\FM\30JNN1.SGM 30JNN1](https://thefederalregister.org/doc/80_FR_37437/page/3.svg)
Document Created: 2018-02-22 11:16:40
Document Modified: 2018-02-22 11:16:40
| Category | Regulatory Information | |
| Collection | Federal Register | |
| sudoc Class | AE 2.7: GS 4.107: AE 2.106: | |
| Publisher | Office of the Federal Register, National Archives and Records Administration | |
| Section | Notices | |
| Action | Design-specific review standard; request for comment. | |
| Dates | Submit comments by August 31, 2015. Comments received after this date will be considered, if it is practical to do so, but the NRC is able to ensure consideration only for comments received on or before this date. | |
| Contact | Jenny Gallo, Office of New Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-7367; email: [email protected] | |
| FR Citation | 80 FR 37312 |
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