RIS 2012-12, Withdrawn NRC Regulatory Issue Summary 2012-12, Licensing Submittal Information and Design Development Activities for Small Modular Reactor Designs: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
 
(Created page by program invented by StriderTol)
 
(7 intermediate revisions by the same user not shown)
Line 3: Line 3:
| issue date = 12/28/2012
| issue date = 12/28/2012
| title = Withdrawn NRC Regulatory Issue Summary 2012-12, Licensing Submittal Information and Design Development Activities for Small Modular Reactor Designs
| title = Withdrawn NRC Regulatory Issue Summary 2012-12, Licensing Submittal Information and Design Development Activities for Small Modular Reactor Designs
| author name = Dudes L A, Muessle M C
| author name = Dudes L, Muessle M
| author affiliation = NRC/NRO/DCIP, NRC/NRR/DPR
| author affiliation = NRC/NRO/DCIP, NRC/NRR/DPR
| addressee name =  
| addressee name =  
Line 9: Line 9:
| docket =  
| docket =  
| license number =  
| license number =  
| contact person = Notich M D
| contact person = Notich M
| document report number = RIS-12-012
| document report number = RIS-12-012
| document type = NRC Regulatory Issue Summary
| document type = NRC Regulatory Issue Summary
| page count = 8
| page count = 8
| revision = 0
}}
}}
{{#Wiki_filter:Withdrawn NRC Regulatory Issue Summary 2012-12, "Licensing Submittal Information and Design Development Activities for Small Modular Reactor Designs," dated December 28, 2012, has been withdraw ADAMS Accession Number: ML12319A181 See Federal Register notice dated October 25, 2016 81 FR 73448 ML12319A181 December 28, 2012 NRC REGULATORY ISSUE SUMMARY 2012-12 LICENSING SUBMITTAL INFORMATION AND DESIGN DEVELOPMENT ACTIVITIES FOR SMALL MODULAR REACTOR DESIGNS  
{{#Wiki_filter:Withdrawn NRC Regulatory Issue Summary 2012-12, Licensing Submittal Information and Design Development Activities for Small Modular Reactor Designs, dated December 28, 2012, has been withdrawn.
 
ADAMS Accession Number: ML12319A181 See Federal Register notice dated October 25, 2016
                      81 FR 73448
 
UNITED STATES
                            NUCLEAR REGULATORY COMMISSION
                          OFFICE OF NUCLEAR REACTOR REGULATION
                                  OFFICE OF NEW REACTORS
                                WASHINGTON, DC 20555-0001 December 28, 2012 NRC REGULATORY ISSUE SUMMARY 2012-12 LICENSING SUBMITTAL INFORMATION AND DESIGN DEVELOPMENT ACTIVITIES
                          FOR SMALL MODULAR REACTOR DESIGNS


==ADDRESSEES==
==ADDRESSEES==
All holders of and applicants for a power reactor early site permit (ESP), combined license (COL), standard design certification (DC), standard design approval (DA), or manufacturing license (ML) referencing a small modular reactor (SMR) design under Title 10 of the Code of Federal Regulations (10 CFR) Part 52, "Licenses, Certifications, and Approvals for Nuclear Power Plants," or all holders of and applicants for a power reactor construction permit (CP) referencing an SMR design under 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities." 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.
All holders of and applicants for a power reactor early site permit (ESP), combined license (COL), standard design certification (DC), standard design approval (DA), or manufacturing license (ML) referencing a small modular reactor (SMR) design under Title 10 of the Code of Federal Regulations (10 CFR) Part 52, Licenses, Certifications, and Approvals for Nuclear Power Plants, or all holders of and applicants for a power reactor construction permit (CP)
referencing an SMR design under 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities. 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==
==INTENT==
The U.S. Nuclear Regulatory Commission (NRC) is issuing this regulatory issue summary (RIS) to obtain new or updated information on the scheduling of CP, ESP, COL, DC, DA, or ML application submissions related to SMR design These designs include integral pressurized-water reactors, high-temperature gas-cooled reactors, liquid-metal-cooled reactors, and other SMR design The purpose of this RIS is to help establish a predictable and consistent method for reviewing application To this end, the NRC also seeks new or updated information on the status of a number of other addressee activities, as discussed belo This RIS follows up on RIS 2011-02, Revision 1, "Licensing Submittal Information and Design Development Activities for Small Modular Reactor Designs," dated December 27, 2011, which seeks similar informatio The staff asks any potential applicant that meets the criteria in the addressee section above also to submit a response to this RI This RIS does not transmit or imply any new or changed requirements or staff position Submission of advanced notice of the addressee's plans or comments in response to this RIS is strictly voluntar 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 activitie
The U.S. Nuclear Regulatory Commission (NRC) is issuing this regulatory issue summary (RIS)
to obtain new or updated information on the scheduling of CP, ESP, COL, DC, DA, or ML
application submissions related to SMR designs. These designs include integral pressurized- water reactors, high-temperature gas-cooled reactors, liquid-metal-cooled reactors, and other SMR designs. The purpose of this RIS is to help establish 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 follows up on RIS 2011-02, Revision 1, Licensing Submittal Information and Design Development Activities for Small Modular Reactor Designs, dated December 27, 2011, which seeks similar information. The staff asks any potential applicant that meets the criteria in the addressee section above also 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.
 
ML12319A181


==BACKGROUND INFORMATION==
==BACKGROUND INFORMATION==
The design-centered review approach (DCRA) is the NRC's strategy to manage the licensing review workload, and the updated information that this RIS solicits will aid the agency's schedule and resource planning effort The NRC outlined the DCRA in RIS 2006-06, "New Reactor Standardization Needed To Support the Design-Centered Licensing Review Approach,"
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 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;
dated May 31, 200 In summary, the DCRA is a review strategy for COL applications that reference a particular desig This approach will use, to the maximum extent practicable, a  
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 generic to SMR designs.
"one issue, one review, one position" strategy to optimize the review effort, the resources needed to perform these reviews, and the review schedule 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 application Applicants must achieve a consistent level of standardization for the DCRA to be fully effectiv 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 generic to SMR design


==SUMMARY OF ISSUE==
==SUMMARY OF ISSUE==
The NRC anticipates receiving a number of CP, ESP, COL, DC, DA, and ML applications, starting as early as 2013, for a number of SMR design RIS 2006-06 suggests that COL and DC applicants form design-centered working groups (DCWGs) to facilitate the standardization of COL application The NRC staff seeks information on potential DCWGs for each of the design As discussed at the October 2009 SMR workshop, this process also may benefit working groups generally associated with SMRs and with specific reactor technologie The NRC is seeking information on the formation of such groups that may interact with the staff on generic or technology-related policy or technical issue The NRC must identify possible applications and other interactions to formulate resource needs and budget requests for future fiscal year 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 the NRC's safety and environmental requirement In addition, information that potential applicants submit to the NRC will allow the agency to coordinate pre-application activities and, as appropriate, conduct vendor audits before the submission of application Furthermore, it will facilitate a more efficient licensing review of the application 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/).
The NRC anticipates receiving a number of CP, ESP, COL, DC, DA, and ML applications, starting as early as 2013, for a number of SMR designs. 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 also may benefit working groups generally associated with SMRs and with specific reactor technologies. The NRC is seeking information on 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 the staff requirements 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 on integral pressurized-water reactors design application 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 activitie Information submitted in response to the questions related to white papers and technical or topical reports will be especially useful in helping the NRC plan and schedule staff activitie
 
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 the NRCs safety and environmental requirements. In addition, information that potential applicants submit to the NRC will allow the agency to coordinate pre-application activities and, as appropriate, conduct vendor audits before the submission of applications.
 
Furthermore, it 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 requirements 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 on integral pressurized-water reactors design applications. 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 or topical reports will be especially useful in helping the NRC plan and schedule staff activities.


==VOLUNTARY RESPONSE==
==VOLUNTARY RESPONSE==
The NRC is developing pre-application, licensing, and project plans for the advanced reactor progra To support this effort, the NRC is seeking new or updated information on schedules for submitting CP, ESP, COL, DC, DA, and ML applications and on the status of a variety of design-related activities for SMR The NRC may share the planned application schedules with other Federal agencies to support its planning efforts on the licensing of new plant 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," must accompany the informatio RIS 2004-11, "Supporting Information Associated with Requests for Withholding Proprietary Information," dated June 29, 2004, provides additional information about requests for withholding proprietary information from public disclosur 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 RI 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 RI 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
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, ESP, COL, DC, DA, and ML applications and on the status of a variety of design-related activities for SMRs. The NRC may share the planned application schedules with other Federal agencies to support its planning efforts on 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, must accompany the information. RIS 2004-11, 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.
* When (month and year) are applications planned for design-related applications and what NRC action will be requested (i.e., a CP, 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?
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:
* Have protocols been developed to provide coordinated responses for requests for additional information with generic applicability to a design center?
Design and Licensing Submittal Information
* 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) are applications planned for design-related applications and what NRC action will be requested (i.e., a CP, DC, DA, or ML, or a COL that does not reference a DC or DA)?
* 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?
*       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?
* 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 activitie Design, Testing, and Application Preparation
*       Have protocols been developed to provide coordinated responses for requests for additional information with generic applicability to a design center?
* 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 schedul
*       Which applicant that references the design will be designated as the reference COL
* What is the applicant's 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 schedul
        applicant, or, alternatively, how will various applications (e.g., CP, DC, or COL
* What is the applicant's 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 and licensing relationships? Has the applicant established a schedule for completing the design and licensing analyses? If so, please describe the schedul
        applications) be coordinated to achieve the desired design-centered licensing review approach?
* What is the applicant's 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 schedul Has the applicant established a schedule for completing the thermal-fluidic testing? If so, please describe the schedul
*       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?
* What is the applicant's 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 schedul
*       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 applicant's status in the development and implementation of a quality assurance program?
*     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 applicant's 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)? Does the applicant plan to use the PRA for any risk-informed applications (i.e., risk-informed technical specifications, risk-informed inservice inspection, risk-informed categorization and treatment, risk-informed inservice testing, etc.). What are the applicant's 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 applicant's status in the development, construction, and use of a control room simulator?
*     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 are the applicant's 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 plan
 
* What are the applicant's plans on the submittal of white papers or technical and topical reports related to the features of its design or the resolution of policy or technical issues?
*     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 and licensing relationships? Has the applicant established a schedule for completing the design and licensing analyses? If so, please describe the schedule.
* Has the applicant established a schedule for submitting such reports? If so, please describe the schedul
 
* 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)?
*     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.
* 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 plan 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?
*     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.
* Describe the expected combination of manufacturing, fabrication, and site construction that results in a completed operational nuclear power plan For example, what systems, structures, and components are being fabricated and delivered? Which of these are being assembled onsite? Which of these are being constructed onsite?
 
*     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)? Does the applicant plan to use the PRA for any risk-informed applications (i.e., risk-informed technical specifications, risk-informed inservice inspection, risk-informed categorization and treatment, risk-informed inservice testing, etc.). 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 and topical reports related to the features of its 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)?
*       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 onsite? Which of these are being constructed onsite?


==Addressees==
==Addressees==
that choose to provide a voluntary response should send it to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-000
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==
==BACKFIT DISCUSSION==
This RIS requires no action or written respons 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 voluntar Therefore, this RIS does not constitute a backfit under 10 CFR 50.109, "Backfitting." Consequently, the staff did not perform a backfit analysi
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===
===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 addressee
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===
===CONGRESSIONAL REVIEW ACT===
The NRC has determined that this RIS is not a rule under the Congressional Review Act (CRA) (5 U.S.C. 801-808) and, therefore, is not subject to the CR
The NRC has determined that this RIS is not a rule under the Congressional Review Act (CRA)
(5 U.S.C. 801-808) and, therefore, is not subject to the CRA.


===PAPERWORK REDUCTION ACT STATEMENT===
===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 existing requirements under OMB control number 3150-001 The NRC estimates that the burden to the public for these voluntary information collections will average 12 hours per response, including the time for reviewing instructions, searching existing data sources, gathering and maintaining the data needed, and completing and reviewing the information collectio 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-5F53), 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, (3150-00011), Office of Management and Budget, Washington, DC 2050
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 existing requirements under OMB control number 3150-0011. The NRC estimates that the burden to the public for these voluntary information collections will average 12 hours 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-5F53), 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, (3150-00011), Office of Management and Budget, Washington, DC 20503.


===PUBLIC PROTECTION NOTIFICATION===
===PUBLIC PROTECTION NOTIFICATION===
The NRC may not conduct or 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 numbe
The NRC may not conduct or 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==
==CONTACT==
Please direct any questions about this matter to the technical contact listed belo /RA/ by JLuehman for /RA/ Laura Dudes, Director Division of Construction Inspection and  Operational Programs Office of New Reactors Mary C. Muessle, Acting Director Division of Policy and Rulemaking Office of Nuclear Reactor Regulation  
Please direct any questions about this matter to the technical contact listed below.
 
/RA/ by JLuehman for                                 /RA/
Laura Dudes, Director                             Mary C. Muessle, Acting Director Division of Construction Inspection and            Division of Policy and Rulemaking Operational Programs                              Office of Nuclear Reactor Regulation Office of New Reactors


===Technical Contact:===
===Technical Contact:===
Mark Notich, Senior Project Manager NRO/DARR/SMRLB1 301-415-3053 E-mail: mark.notich@nrc.gov Note: NRC generic communications may be found on the NRC public Web site, http://www.nrc.gov, under the headings "NRC Library," "Document Collections."
Mark Notich, Senior Project Manager NRO/DARR/SMRLB1
                        301-415-3053 E-mail: mark.notich@nrc.gov Note: NRC generic communications may be found on the NRC public Web site, http://www.nrc.gov, under the headings NRC Library, Document Collections. The NRC estimates that the burden to the public for these voluntary information collections will average 12 hours 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-5F53), 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, (3150-00011), Office of Management and Budget, Washington, DC 20503.


RIS 2012-12  OFFICE PM:NRO/DARR/SMRLB1 LA:NRO/DARR/SMRLB1 BC:NRO/DARR/SMRLB1 Tech Editor* D:NRO/DARR NAME MNotich RRobinson* SMagruder CHsu MMayfield DATE 11/14/12 11/15/12 11/29/12 11/26/12 11/27/12 OFFICE D:NRO/PMDA D:OIS OE* OGC* LA:NRR/DPR* NAME BGusack (MTonacci for) TDonnell NHilton (RFretz for) MCarpentier CHawes DATE 12/8/12 12/13/12 12/19/12 12/19/12 12/21/12 OFFICE PM:NRR/DPR/PGCB BC:NRR/DPR/PGCB D:NRO/DCIP (A)D:NRR/DPR NAME TAlexion DPelton (EBowman for) LDudes (JLuehman for) MMuessle DATE 12/21/12 12/26/12 12/27/12 12/28/12
===PUBLIC PROTECTION NOTIFICATION===
The NRC may not conduct or 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 JLuehman for                                          /RA/
  Laura Dudes, Director                                    Mary C. Muessle, Acting Director Division of Construction Inspection and                  Division of Policy and Rulemaking Operational Programs                                    Office of Nuclear Reactor Regulation Office of New Reactors
 
===Technical Contact:===
Mark Notich, Senior Project Manager NRO/DARR/SMRLB1
                              301-415-3053 E-mail: mark.notich@nrc.gov Note: NRC generic communications may be found on the NRC public Web site, http://www.nrc.gov, under the headings NRC Library, Document Collections.


DISTRIBUTION:              PUBLIC          DARR R/F
  ADAMS Accession Number: ML12319A181                *via e-mail                                  NRO-002 OFFICE  PM:NRO/DARR/SMRLB1      LA:NRO/DARR/SMRLB1    BC:NRO/DARR/SMRLB1    Tech Editor* D:NRO/DARR
NAME    MNotich                  RRobinson*            SMagruder              CHsu        MMayfield DATE    11/14/12                11/15/12              11/29/12              11/26/12    11/27/12 OFFICE  D:NRO/PMDA              D:OIS                  OE*                    OGC*        LA:NRR/DPR*
NAME    BGusack (MTonacci for)  TDonnell              NHilton (RFretz for)  MCarpentier  CHawes DATE    12/8/12                  12/13/12              12/19/12              12/19/12    12/21/12 OFFICE  PM:NRR/DPR/PGCB          BC:NRR/DPR/PGCB        D:NRO/DCIP            (A)D:NRR/DPR
NAME    TAlexion                DPelton (EBowman for)  LDudes (JLuehman for)  MMuessle DATE    12/21/12                12/26/12              12/27/12              12/28/12 OFFICIAL RECORD COPY
}}
}}


{{RIS-Nav}}
{{RIS-Nav}}

Latest revision as of 21:05, 11 November 2019

Withdrawn NRC Regulatory Issue Summary 2012-12, Licensing Submittal Information and Design Development Activities for Small Modular Reactor Designs
ML12319A181
Person / Time
Issue date: 12/28/2012
From: Laura Dudes, Mary Muessle
Division of Construction Inspection and Operational Programs, Division of Policy and Rulemaking
To:
Notich M
References
RIS-12-012
Preceding documents:
Download: ML12319A181 (8)


Withdrawn NRC Regulatory Issue Summary 2012-12, Licensing Submittal Information and Design Development Activities for Small Modular Reactor Designs, dated December 28, 2012, has been withdrawn.

ADAMS Accession Number: ML12319A181 See Federal Register notice dated October 25, 2016

81 FR 73448

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

OFFICE OF NEW REACTORS

WASHINGTON, DC 20555-0001 December 28, 2012 NRC REGULATORY ISSUE SUMMARY 2012-12 LICENSING SUBMITTAL INFORMATION AND DESIGN DEVELOPMENT ACTIVITIES

FOR SMALL MODULAR REACTOR DESIGNS

ADDRESSEES

All holders of and applicants for a power reactor early site permit (ESP), combined license (COL), standard design certification (DC), standard design approval (DA), or manufacturing license (ML) referencing a small modular reactor (SMR) design under Title 10 of the Code of Federal Regulations (10 CFR) Part 52, Licenses, Certifications, and Approvals for Nuclear Power Plants, or all holders of and applicants for a power reactor construction permit (CP)

referencing an SMR design under 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities. 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 regulatory issue summary (RIS)

to obtain new or updated information on the scheduling of CP, ESP, COL, DC, DA, or ML

application submissions related to SMR designs. These designs include integral pressurized- water reactors, high-temperature gas-cooled reactors, liquid-metal-cooled reactors, and other SMR designs. The purpose of this RIS is to help establish 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 follows up on RIS 2011-02, Revision 1, Licensing Submittal Information and Design Development Activities for Small Modular Reactor Designs, dated December 27, 2011, which seeks similar information. The staff asks any potential applicant that meets the criteria in the addressee section above also 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.

ML12319A181

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 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 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 generic to SMR designs.

SUMMARY OF ISSUE

The NRC anticipates receiving a number of CP, ESP, COL, DC, DA, and ML applications, starting as early as 2013, for a number of SMR designs. 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 also may benefit working groups generally associated with SMRs and with specific reactor technologies. The NRC is seeking information on 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 the NRCs safety and environmental requirements. In addition, information that potential applicants submit to the NRC will allow the agency to coordinate pre-application activities and, as appropriate, conduct vendor audits before the submission of applications.

Furthermore, it 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 requirements 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 on integral pressurized-water reactors design applications. 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 or topical reports will be especially useful in helping the NRC plan and schedule staff activities.

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, ESP, COL, DC, DA, and ML applications and on the status of a variety of design-related activities for SMRs. The NRC may share the planned application schedules with other Federal agencies to support its planning efforts on 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, must accompany the information. RIS 2004-11, 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 CP, 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.
  • 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 and 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?

models needed to support applications (e.g., needed for Chapter 19 of safety analysis reports or needed to support risk-informed licensing approaches)? Does the applicant plan to use the PRA for any risk-informed applications (i.e., risk-informed technical specifications, risk-informed inservice inspection, risk-informed categorization and treatment, risk-informed inservice testing, etc.). 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 and topical reports related to the features of its 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.
  • 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 onsite? Which of these are being constructed onsite?

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 (CRA)

(5 U.S.C. 801-808) and, therefore, is not subject to the CRA.

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 existing requirements under OMB control number 3150-0011. 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-5F53), 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, (3150-00011), Office of Management and Budget, Washington, DC 20503.

PUBLIC PROTECTION NOTIFICATION

The NRC may not conduct or 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 JLuehman for /RA/

Laura Dudes, Director Mary C. Muessle, Acting Director Division of Construction Inspection and Division of Policy and Rulemaking Operational Programs Office of Nuclear Reactor Regulation Office of New Reactors

Technical Contact:

Mark Notich, Senior Project Manager NRO/DARR/SMRLB1

301-415-3053 E-mail: mark.notich@nrc.gov Note: NRC generic communications may be found on the NRC public Web site, http://www.nrc.gov, under the headings NRC Library, Document Collections. 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-5F53), 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, (3150-00011), Office of Management and Budget, Washington, DC 20503.

PUBLIC PROTECTION NOTIFICATION

The NRC may not conduct or 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 JLuehman for /RA/

Laura Dudes, Director Mary C. Muessle, Acting Director Division of Construction Inspection and Division of Policy and Rulemaking Operational Programs Office of Nuclear Reactor Regulation Office of New Reactors

Technical Contact:

Mark Notich, Senior Project Manager NRO/DARR/SMRLB1

301-415-3053 E-mail: mark.notich@nrc.gov Note: NRC generic communications may be found on the NRC public Web site, http://www.nrc.gov, under the headings NRC Library, Document Collections.

DISTRIBUTION: PUBLIC DARR R/F

ADAMS Accession Number: ML12319A181 *via e-mail NRO-002 OFFICE PM:NRO/DARR/SMRLB1 LA:NRO/DARR/SMRLB1 BC:NRO/DARR/SMRLB1 Tech Editor* D:NRO/DARR

NAME MNotich RRobinson* SMagruder CHsu MMayfield DATE 11/14/12 11/15/12 11/29/12 11/26/12 11/27/12 OFFICE D:NRO/PMDA D:OIS OE* OGC* LA:NRR/DPR*

NAME BGusack (MTonacci for) TDonnell NHilton (RFretz for) MCarpentier CHawes DATE 12/8/12 12/13/12 12/19/12 12/19/12 12/21/12 OFFICE PM:NRR/DPR/PGCB BC:NRR/DPR/PGCB D:NRO/DCIP (A)D:NRR/DPR

NAME TAlexion DPelton (EBowman for) LDudes (JLuehman for) MMuessle DATE 12/21/12 12/26/12 12/27/12 12/28/12 OFFICIAL RECORD COPY