ML110620515
| ML110620515 | |
| Person / Time | |
|---|---|
| Issue date: | 02/01/2011 |
| From: | Blount T, Mayfield M NRC/NRO/ARP, Division of Policy and Rulemaking |
| To: | |
| Held W, NRO/ARP/ARB1, 415-1583 | |
| Shared Package | |
| ML110620468 | List: |
| References | |
| RIS-11-002 | |
| Download: ML110620515 (8) | |
See also: RIS 2011-02
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NEW REACTORS
WASHINGTON, DC 20555-0001
February 2, 2011
NRC REGULATORY ISSUE SUMMARY 2011-02
LICENSING SUBMITTAL INFORMATION AND DESIGN DEVELOPMENT ACTIVITIES
FOR SMALL MODULAR REACTOR DESIGNS
ADDRESSEES
All applicants for a construction permit (CP), early site permit (ESP), combined license (COL),
standard design certification (DC), standard design approval (DA), or manufacturing license
(ML) for a nuclear power plant that references a small modular reactor (SMR) design under the
provisions of Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Domestic Licensing
of Production and Utilization Facilities, or 10 CFR Part 52, Licenses, Certifications, and
Approvals for Nuclear Power Plants. For the purpose of this regulatory issue summary (RIS),
SMRs are defined using the International Atomic Energy Agency definition of small- and
medium-sized reactors with an electrical output of less than 700 megawatts.
INTENT
The U.S. Nuclear Regulatory Commission (NRC) is issuing this RIS to obtain new or updated
information on the scheduling of CP, ESP, COL, DC, DA, or ML application submissions related
to advanced reactor designs. These designs include integral pressurized-water reactors, high-
temperature gas-cooled reactors, liquid-metal-cooled reactors, and other small- or medium-
sized reactor designs. The purpose of this RIS is to facilitate the establishment of a predictable
and consistent method for reviewing applications. To this end, the NRC also seeks new or
updated information on the status of a number of other addressee activities as discussed below.
This RIS is a follow-on to RIS 2010-03, Licensing Submittal Information for Small Modular
Reactor Designs dated February 25, 2010, which seeks similar information. The staff asks any
potential applicant that meets the criteria in the addressee section above to also submit a
response to this RIS.
This RIS does not transmit or imply any new or changed requirements or staff positions.
Submission of advanced notice of the addressees plans or comments in response to this RIS is
strictly voluntary. Although no specific action or written response is required, this information
will enable the NRC to plan effectively for anticipated licensing-related review and inspection
activities.
BACKGROUND INFORMATION
The design-centered review approach (DCRA) is the NRCs strategy to manage the licensing
review workload, and the updated information that this RIS solicits will aid the agencys
Page 2 of 7
schedule and resource planning efforts. The NRC outlined the DCRA in RIS 2006-06, New
Reactor Standardization Needed to Support the Design-Centered Licensing Review Approach,
dated May 31, 2006. In summary, the DCRA is a review strategy for COL applications that
reference a particular design. This approach will use, to the maximum extent practicable, a
one issue, one review, one position strategy to optimize the review effort, the resources
needed to perform these reviews, and the review schedules. Specifically, the staff will conduct
one review for each issue associated with a particular design, reach a decision on each issue,
and if possible rely on that decision in reviewing subsequent applications. Applicants must
achieve a consistent level of standardization for the DCRA to be fully effective. As discussed at
an NRC-sponsored workshop in October 2009 on SMRs, the philosophy of one issue, one
review, one position can also be used across designs and reactor technologies to address
policy or technical issues generally associated with SMRs.
SUMMARY OF ISSUE
The NRC anticipates receiving a number of CP, ESP, DC, DA, ML, and COL applications
starting as early as 2012 for a number of advanced reactor designs. The review of these
advanced reactor designs will require the resolution of a number of important policy and
technical issues. The NRC expects that many of these issues will require an indepth review and
that the resolution of some issues will involve decisions by the Commission.
RIS 2006-06 suggests that COL and DC applicants form design-centered working groups
(DCWGs) to facilitate the standardization of COL applications. The NRC staff seeks information
on potential DCWGs for each of the designs. As discussed at the October 2009 SMR
workshop, this process may also be beneficial for working groups generally associated with
SMRs and with specific reactor technologies. The NRC would appreciate information about the
formation of such groups that may interact with the staff on generic or technology-related policy
or technical issues. The NRC must identify possible applications and other interactions to
formulate resource needs and budget requests for future fiscal years. In addition, the NRC staff
expects to issue requests for additional information (RAIs) to complete its reviews. The staff
seeks standardized responses to RAIs associated with applications consistent with the DCWGs
or generic or technology-related working groups. Applicants will need to adhere to a specified
RAI response period, including coordination within the DCWG or other working groups, to
enable the NRC to maintain its anticipated review schedules.
The NRC encourages potential applicants to provide the agency with design and licensing
plans, construction plans, and preapplication activities that will be used to demonstrate
compliance with NRC safety and environmental requirements, such as quality assurance
requirements. In addition, information that potential applicants submit to the NRC will allow it to
coordinate preapplication activities and, as appropriate, conduct vendor audits before the
submission of applications. Furthermore, information on vendors and consultants that assist in
the preparation of the application will facilitate a more efficient licensing review of the
applications. Regulatory Position C.IV.7 in Regulatory Guide 1.206, Combined License
Applications for Nuclear Power Plants (LWR Edition), issued June 2007, provides more
information on preapplication activities (http://www.nrc.gov/reading-rm/doc-collections/reg-
guides/power-reactors/rg/01-206/).
Page 3 of 7
VOLUNTARY RESPONSE
The NRC is developing preapplication, licensing, and project plans for the advanced reactor
program. To support this effort, the NRC is seeking new or updated information on schedules
for submitting CP, DC, DA, ML, ESP, and COL applications and on the status of a variety of
design-related activities for small- and medium-sized reactors. The NRC may share the
planned application schedules with other Federal agencies to support its planning efforts related
to the licensing of new plants. If a prospective applicant deems this information proprietary, a
request to withhold information from public disclosure in accordance with 10 CFR 2.390, Public
Inspections, Exemptions, Request for Withholding, may accompany the information.
RIS 2004-011, Supporting Information Associated with Requests for Withholding Proprietary
Information, dated June 29, 2004, provides additional information about requests for
withholding proprietary information from public disclosure. The NRC requests that potential
applicants request withholding only for information that they currently treat as proprietary and,
provide, where necessary, the proprietary information in designated attachments to their
response to this RIS.
If an addressee chooses to provide a voluntary response, the NRC would like to obtain the
information within 45 days of the date of this RIS. Respondents should provide the NRC with
the information outlined below, based on realistic, best estimate predictions of applications or
other submittals.
Design and Licensing Submittal Information
- When (month and year) are applications planned for design-related applications and
what NRC action will be requested (i.e., DC, DA, ML, or COL that does not reference a
- Will the applicants be organized into DCWGs? If known, what is the membership of the
DCWG and which party is the primary point-of-contact designated for each DCWG?
Have protocols been developed to provide coordinated responses for RAIs with generic
applicability to a design center?
- Which applicant that references the design will be designated as the reference COL
applicant or, alternatively, how will various applications (e.g., CP, DC, COL) be
coordinated to achieve the desired design-centered licensing review approach?
addition, what are the design, site location, and number of units at each site?
- Are vendors or consultants assisting in the preparation of the application(s)? If so,
please describe roles and responsibilities for the design and licensing activities.
Page 4 of 7
Design, Testing, and Application Preparation
- What is the current status of the development of the plant design (i.e., conceptual,
preliminary, or finalizing)? Has the applicant established a schedule for completing the
design? If so, please describe the schedule.
- What is the applicants current status (i.e., planning, in progress, or complete) for the
qualification of fuel and other major systems and components? Has the applicant
established a schedule for completing the qualification testing? If so, please describe
the schedule.
- What is the applicants status (i.e., planning, in progress, or complete) in developing
computer codes and models to perform design and licensing analyses? Has the
applicant defined principal design criteria, licensing-basis events, and other fundamental
design/licensing relationships? Has the applicant established a schedule for completing
the design and licensing analyses? If so, please describe the schedule.
- What is the applicants status in designing, constructing, and using thermal-fluidic testing
facilities and in using such tests to validate computer models? Has the applicant
established a schedule for the construction of testing facilities? If so, please describe
the schedule. Has the applicant established a schedule for completing the thermal-
fluidic testing? If so, please describe the schedule.
- What is the applicants status in defining system and component suppliers (including
fuel), manufacturing processes, and other major factors that could influence design
decisions? Has the applicant established a schedule for identifying suppliers and key
contractors? If so, please describe the schedule.
- What is the applicants status in the development and implementation of a quality
assurance program?
- What is the applicants status in the development of probabilistic risk assessment
models needed to support applications (e.g., needed for Chapter 19 of safety analysis
reports or needed to support risk-informed licensing approaches)? What are the
applicants plans for using the probabilistic risk assessment models in the development
of the design?
- What is the applicants status in the development, construction, and use of a control
room simulator?
- What are the applicants current staffing levels (e.g., full-time equivalent staff) for the
design and testing of the reactor design? Does the applicant have plans to increase
staffing? If so, please describe future staffing plans.
- What are the applicants current and future plans for using contractors to support plant
design and testing (e.g., how many part-time and full-time contractors does or will the
applicant employ)?
Page 5 of 7
White Papers and Technical/Topical Reports
- What are the applicants plans on the submittal of white papers or technical/topical
reports related to the features of their design or the resolution of policy or technical
issues? Has the applicant established a schedule for submitting such reports? If so,
please describe the schedule.
- For ESP applicants, will the applicant seek approval of either proposed major features
of the emergency plans in accordance with 10 CFR 52.17(b)(2)(i) or proposed
complete and integrated emergency plans in accordance with 10 CFR 52.17(b)(2)(ii)?
Manufacturing Licenses
- Describe possible interest in the use of the provisions in Subpart F, Manufacturing
Licenses, of 10 CFR Part 52 instead of, or in combination with, other licensing
- Describe the expected combination of manufacturing, fabrication, and site construction
that results in a completed operational nuclear power plant. For example, what systems,
structures, and components are being fabricated and delivered; which of these are being
assembled on site; and which are being constructed on site?
- Describe the desired scope of a possible manufacturing license and what design or
licensing process would address the remainder of the proposed nuclear power plant.
For example, would the manufacturing license address an essentially complete plant or
would it be limited to the primary coolant system basically consisting of the integral
reactor vessel and internals?
Addressees that choose to provide a voluntary response should send it to the U.S. Nuclear
Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001.
BACKFIT DISCUSSION
This RIS requires no action or written response. Any action on the part of addressees to
provide information on standardization or advanced notice of intent to pursue a COL in
accordance with the guidance contained in this RIS aids the NRC in planning the use of its
resources and is strictly voluntary. Therefore, this RIS does not constitute a backfit under
10 CFR 50.109, Backfitting, and the staff did not perform a backfit analysis.
FEDERAL REGISTER NOTIFICATION
The NRC did not publish a notice of opportunity for public comment on this RIS in the Federal
Register because the RIS pertains to an administrative aspect of the regulatory process that
involves the voluntary submission of information on the part of addressees.
Page 6 of 7
CONGRESSIONAL REVIEW ACT
The NRC has determined that this action is not a rule as designated by the Congressional
Review Act (5 U.S.C. §§ 801-808) and, therefore, is not subject to the Act.
PAPERWORK REDUCTION ACT STATEMENT
This RIS contains information collection requirements that are subject to the Paperwork
Reduction Act of 1995 (44 U.S.C. 3501 et seq.). These information collections were approved
by the Office of Management and Budget (OMB) under OMB control numbers 3150-0011 and
3150-0151.
The NRC estimates that the burden to the public for these voluntary information collections will
average 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per response, including the time for reviewing instructions, searching existing
data sources, gathering and maintaining the data needed, and completing and reviewing the
information collection. Send comments on this burden estimate or any other aspects of these
information collections, including suggestions for reducing the burden, to the Information
Services Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001, or by e-mail to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office of
Information and Regulatory Affairs, NEOB-10202, (3150-0011), Office of Management and
Budget, Washington, DC 20503.
PUBLIC PROTECTION NOTIFICATION
The NRC may neither conduct nor sponsor, and a person is not required to respond to, an
information collection request or requirement unless the requesting document displays a
currently valid OMB control number.
Page 7 of 7
CONTACT
Please direct any questions about this matter to the technical contact listed below.
/RA/
Michael E. Mayfield, Director
Advanced Reactor Program
Office of New Reactors
/RA/
Thomas B. Blount, Acting Director
Division of Policy and Rulemaking
Office of Nuclear Reactor Regulation
Technical Contact: Wesley W. Held, Project Manager
NRO/ARP/ARB1
(301) 415-1583
E-mail: wesley.held@nrc.gov
Note: NRC generic communications may be found on the NRC public Web site,
http://www.nrc.gov, under Electronic Reading Room/Document Collections.
Page 7 of 7
CONTACT
Please direct any questions about this matter to the technical contact listed below.
/RA/
Michael E. Mayfield, Director
Advanced Reactor Program
Office of New Reactors
/RA/
Thomas B. Blount, Acting Director
Division of Policy and Rulemaking
Office of Nuclear Reactor Regulation
Technical Contact: Wesley W. Held, Project Manager
NRO/ARP/ARB1
(301) 415-1583
E-mail: wesley.held@nrc.gov
Note: NRC generic communications may be found on the NRC public Web site,
http://www.nrc.gov, under Electronic Reading Room/Document Collections
DISTRIBUTION:
PUBLIC
ARP R/F RidsOeMailCenter RidsNroArp
MMayfield, NRO RidsOgcMailCenter RidsNroArpArb2
SMagruder, NRO RidsOIS RidsNroArpArb1
WReckley, NRO RidsNroOd
ADAMS Accession Number: ML103260128 *via e-mail NRO-002
OFFICE NRO/ARP/ARB1 Tech Editor* NRO/ARP/ARB1 OGC/CRA OE
TRothschild (SCrockett NHilton (CFaria-Ocasio
NAME WHeld KAzariah-Kribbs* WReckley*
for)* for) *
DATE 11/19/10 11/29/10 1/26 /11 1/18 /11 1/20/11
OFFICE NRO/PMDA OIS NRO/ARP OGC/NLO NRR/DPR/LA
MZobler (SVrahoretis
NAME BGusack TDonnell * MMayfield CHawes* CMH
for)
DATE 1/21/11 1/13 /11 1/25/11 1/25 /11 1/28/11
OFFICE NRR/DPR/PGCB NRR/DPR/PGCB NRR/DPR
NAME TMensah SRosenburg TBlount
DATE 1/31/11 1/31/11 2/1/11
OFFICIAL RECORD COPY