[Federal Register Volume 78, Number 93 (Tuesday, May 14, 2013)]
[Notices]
[Pages 28258-28262]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2013-11394]
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NUCLEAR REGULATORY COMMISSION
[NRC-2013-0089]
mPower\TM\ Design-Specific Review Standard
AGENCY: Nuclear Regulatory Commission.
ACTION: Design-Specific Review Standard (DSRS) for the mPower\TM\
Design; request for comment.
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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is soliciting
public comment on the Design-Specific Review Standard (DSRS) for the
mPower\TM\ design (mPower\TM\ DSRS). The purpose of the mPower\TM\ DSRS
is to more fully integrate the use of risk insights into the review of
a design certification (DC), an early site permit (ESP) or a combined
license (COL) that incorporates the mPower\TM\ design.
DATES: Submit comments by August 16, 2013. Comments received after this
date will be considered, if it is practical to do so, but the
Commission is able to ensure consideration only for comments received
on or before this date.
ADDRESSES: You may submit comment by any of the following methods
(unless this document describes a different method for submitting
comments on a specific subject):
Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2013-0089. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-492-
3668; email: [email protected]. 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 [email protected].
SUPPLEMENTARY INFORMATION:
I. Accessing Information and Submitting Comments
A. Accessing Information
Please refer to Docket ID NRC-2013-0089 when contacting the NRC
about the availability of information regarding this document. You may
access information related to this document, which the NRC possesses
and is publicly-available, by the following methods:
Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2013-0089.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may access publicly-available documents online in the NRC
Library at http://www.nrc.gov/reading-rm/adams.html. To begin the
search, select ``ADAMS Public Documents'' and then select ``Begin Web-
based ADAMS Search.'' For problems with ADAMS, please contact the NRC's
Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-
4737, or by email to [email protected]. The ADAMS accession number
for each document referenced in this notice (if that document is
available in ADAMS) is provided the first time that a document is
referenced and also in the table included in this notice. The
mPower\TM\ DSRS Scope and Safety Review Matrix is available in ADAMS
under Accession No. ML13088A252.
NRC's PDR: You may examine and purchase copies of public
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555
Rockville Pike, Rockville, Maryland 20852.
B. Submitting Comments
Please include Docket ID NRC-2013-0089 in the subject line of your
comment submission, in order to ensure that the NRC is able to make
your comment submission available to the public in this docket.
The NRC cautions you not to include identifying or contact
information that you do not want to be publicly disclosed in your
comment submission. The NRC posts all comment submissions at http://www.regulations.gov as well as entering the comment submissions into
ADAMS. The NRC does not routinely edit comment submissions to remove
identifying or contact information.
If you are requesting or aggregating comments from other persons
for submission to the NRC, then you should inform those persons not to
include identifying or contact information that they do not want to be
publicly disclosed in their comment submission. Your request should
state that the NRC does not routinely edit comment submissions to
remove such information before making the comment submissions available
to the public or entering the comment submissions into ADAMS.
II. Further Information
A. Background
In 2010, the Commission provided direction to the staff on the
preparation for, and review of, small modular reactor (SMR)
applications, with a near-term focus on integral pressurized water
reactor (iPWR) designs. The Commission directed the staff to more fully
integrate the use of risk insights into pre-application activities and
the review of applications and, consistent with regulatory requirements
and Commission policy statements, to align the review focus and
resources to risk-significant structures, systems, and components and
other aspects of the design that contribute most to safety in order to
enhance the effectiveness and efficiency of the review process. The
Commission directed the staff to develop a design-specific, risk-
informed review plan for each SMR design to address pre-application and
application review activities. An important part of this review plan is
the Design-Specific Review Standard. This DSRS for the mPower\TM\
design is the result of the implementation of the Commission's
direction.
B. Design-Specific Review Standard (DSRS) for the mPower\TM\ Design
As part of the mPower\TM\ Design-Specific Review Plan, the Office
of New Reactors has issued the mPower\TM\ Design-Specific Review
Standard Scope and Safety Review Matrix to reflect the integration of
risk insights into the review of applications submitted for the
mPower\TM\ DC, and ESPs or COLs that incorporate the mPower\TM\ design
under 10 CFR Part 52. The mPower\TM\ DSRS reflects current staff review
methods and practices based on the integration of risk insights and,
where appropriate, lessons learned from NRC reviews of DC and COL
applications completed since the last revision of the Standard Review
Plan.
The NRC staff is issuing this notice to solicit public comment on
the mPower\TM\ DSRS Scope and Safety Review Matrix (Matrix), and the
individual mPower\TM\-specific DSRS sections. Specifically, we request
comment on the sufficiency of the proposed mPower\TM\ review scope
encompassed by the Matrix, and comment on technical content of the
individual mPower\TM\ DSRS sections identified in the table below that
were revised or developed to incorporate design-specific review
guidance based on features of the mPower\TM\ reactor design. We are
not, however, soliciting detailed technical comments on NUREG-0800
Standard Review Plan sections that are designated with the
applicability ``A) Use SRP Section as-is . . .'' in the Matrix unless
their adequacy for review of the mPower\TM\ design is in question.
------------------------------------------------------------------------
Design-specific review
Section standard title ADAMS No.
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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.
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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