RIS 2011-02, Withdrawn NRC Regulatory Issue Summary 2011-02, Revision 1 Licensing Submittal Information and Design Development Activities for Small Modular Reactor Designs
| ML112930188 | |
| Person / Time | |
|---|---|
| Issue date: | 12/27/2011 |
| Revision: | 1 |
| From: | Laura Dudes, Mcginty T Division of Construction Inspection and Operational Programs, Division of Policy and Rulemaking |
| To: | |
| Samina Shaikh, NRO/ARP, 415-6763 | |
| References | |
| RIS-11-002, Rev 1 | |
| Preceding documents: |
|
| Download: ML112930188 (8) | |
Withdrawn NRC Regulatory Issue Summary 2011-02, Rev. 1, Licensing Submittal Information and Design Development Activities for Small Modular Reactor Designs, dated December 27, 2011, has been withdrawn.
ADAMS Accession Number: ML112930188 See Federal Register notice dated October 25, 2016
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NEW REACTORS
WASHINGTON, DC 20555-0001 December 27, 2011 NRC REGULATORY ISSUE SUMMARY 2011-02, REVISION 1 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 and status of potential submittals for CP, ESP, COL, DC, DA, or ML applications related to SMR designs. These designs include integral pressurized-water reactors (iPWRs), high-temperature gas-cooled reactors, liquid-metal-cooled reactors, and other small- or medium-sized reactor designs. The purpose of this RIS is to allow the NRC staff to gain enough information regarding addressee plans to support the NRC budget development process and to effectively develop review plans. To this end, the NRC also seeks new or updated information on the status of other addressee activities as discussed in the questions below. This RIS is a follow-on to RIS 2011-02, Licensing Submittal Information and Design Development Activities for Small Modular Reactor Designs, dated February 2, 2011, which sought similar information. The staff asks any potential applicant that meets the criteria in the addressee section above to 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.
RIS 2011-02, Rev. 1
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 help the agency in its schedule and resource planning efforts. The NRC outlined the DCRA in RIS 2006-006, 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 on SMRs in October 2009, the philosophy of one issue, one review, one position can also be used across designs and reactor technologies to address policy or technical issues that are generic to SMR designs.
SUMMARY OF ISSUE
The NRC anticipates receiving a number of CP, ESP, DC, DA, ML, and COL applications starting as early as 2013 for a number of SMR designs. RIS 2006-006 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 benefit working groups generally associated with SMRs and with specific reactor technologies. The NRC is seeking 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.
The NRC encourages potential applicants to provide the agency with design and licensing plans, construction plans, and pre-application 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 pre-application 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 pre-application activities (http://www.nrc.gov/reading-rm/doc-collections/reg- guides/power-reactors/rg/01-206/).
In the Staff Requirement Memorandum on SECY-11-0024, Use of Risk Insights to Enhance the Safety Focus of Small Modular Reactor Reviews, dated May 11, 2011, the Commission directed the staff to use the risk-informed and integrated review framework for staff pre-application and application review activities pertaining to iPWR design applications. In order to do this effectively, and to take advantage of lessons-learned from recently completed reactor design reviews, the staff expects to expand the scope of pre-application activities. Information submitted in response to the questions related to White Papers and Technical/Topical Reports will be especially useful in planning and scheduling staff activities.
RIS 2011-02, Rev. 1
VOLUNTARY RESPONSE
The NRC is developing pre-application, 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 asks potential applicants to request withholding only for information that they currently treat as proprietary and to 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 following information, 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., a DC, DA, or ML or a COL that does not reference a DC or DA)?
- 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 requests for additional information 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, or COL
applications) be coordinated to achieve the desired design-centered licensing review approach?
- When (month and year) will CP, COL, or ESP applications be submitted for review? In 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 their roles and responsibilities for the design and licensing activities.
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.
RIS 2011-02, Rev. 1
- 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 (PRA)
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 PRA models in the development of the design? At what level will the PRA be prepared and when will it be submitted in the application process?
- 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 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.
- Will ESP applicants 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)?
RIS 2011-02, Rev. 1 * 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 approaches (e.g., DC or DA).
- Describe the desired scope of a possible ML and what design or licensing process would address the remainder of the proposed nuclear power plant. For example, would the ML
address an essentially complete plant or would it be limited to the primary coolant system that basically comprises the integral reactor vessel and internals?
- 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? Which of these are being constructed on site?
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 CP, ESP, COL,
DC, DA, or ML in accordance with the guidance contained in this RIS helps the NRC to plan its resources and is strictly voluntary. Therefore, this RIS does not constitute a backfit under
10 CFR 50.109, Backfitting. Consequently, 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 it pertains to an administrative aspect of the regulatory process that involves the voluntary submission of information on the part of addressees.
CONGRESSIONAL REVIEW ACT
The NRC has determined that this RIS is not a rule under 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.). The Office of Management and Budget (OMB)
approved these information collections 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
RIS 2011-02, Rev. 1 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 and 3150-0151), 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, a request for information or an information collection requirement unless the requesting document displays a currently valid OMB control number.
CONTACT
Please direct any questions about this matter to the technical contact listed below.
/RA by JTappert for/ /RA by RNelson for/
Laura Dudes, Director Timothy J. McGinty, Director Division of Construction Inspection and Division of Policy and Rulemaking Operational Programs Office of Nuclear Reactor Regulation Office of New Reactors
Technical Contact:
Samina Shaikh, Project Manager NRO/ARP/ARB2
(301) 415-6763 E-mail: samina.shaikh@nrc.gov Note: NRC generic communications may be found on the NRC public Web site, http://www.nrc.gov, under NRC Library/Document Collections
RIS 2011-02, Rev. 1 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 and 3150-0151), 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, a request for information or an information collection requirement unless the requesting document displays a currently valid OMB control number.
CONTACT
Please direct any questions about this matter to the technical contact listed below.
/RA by JTappert for/ /RA by RNelson for/
Laura Dudes, Director Timothy J. McGinty, Director Division of Construction Inspection and Division of Policy and Rulemaking Operational Programs Office of Nuclear Reactor Regulation Office of New Reactors
Technical Contact:
Samina Shaikh, Project Manager NRO/ARP/ARB2
(301) 415-6763 E-mail: samina.shaikh@nrc.gov Note: NRC generic communications may be found on the NRC public Web site, http://www.nrc.gov, under NRC Library/Document Collections DISTRIBUTION:
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