ML20281A761
ML20281A761 | |
Person / Time | |
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Issue date: | 10/15/2020 |
From: | Amy Cubbage NRC/NRR/DANU/UARP |
To: | |
Cubbage A, NRR/DANU/UARP, 301-415-2875 | |
References | |
Download: ML20281A761 (9) | |
Text
DRAFT Preapplication Engagement to Optimize Application Reviews This draft staff white paper has been prepared and is being released to support ongoing public discussions.
This paper has not been subject to NRC management and legal reviews and approvals, and its contents are subject to change and should not be interpreted as official agency positions.
Purpose:
The NRC staff is publishing this paper to provide information to advanced reactor developers on the benefits of robust preapplication engagement in order to optimize application reviews.
Background:
In accordance with the Advanced Reactor Policy Statement1, the NRC encourages early interactions with advanced reactor developers and prospective applicants.
The Policy states:
To provide for more timely and effective regulation of advanced reactors, the Commission encourages the earliest possible interaction of applicants, vendors, other government agencies, and the NRC to provide for early identification of regulatory requirements for advanced reactors and to provide all interested parties, including the public, with a timely, independent assessment of the safety and security characteristics of advanced reactor designs. Such licensing interaction and guidance early in the design process will contribute towards minimizing complexity and adding stability and predictability in the licensing and regulation of advanced reactors.
Further, Section 103 of the Nuclear Energy Innovation and Modernization Act (NEIMA) included requirements that the NRC (1) include the use of topical reports, standard design approval, and other appropriate mechanisms as tools to introduce stages into the commercial advanced nuclear reactor licensing process; (2) evaluate options for improving the efficiency, timeliness, and cost-effectiveness of licensing reviews of commercial advanced nuclear reactors, including opportunities to minimize the delays that may result from any necessary amendment or supplement to an application; and (3) options for improving the predictability of the commercial advanced nuclear reactor licensing process, including the evaluation of opportunities to improve the process by which application review milestones are established and met. Robust pre-application engagement is key to fulfilling these requirements..
NRC encourages pre-application interactions with advanced reactor developers to provide stability and predictability in the licensing process through early identification and resolution of technical and policy issues that would affect licensing. As such, the NRC staff is proposing a set of pre-application activities that, if fully executed, will enable staff to offer more predictable and shorter schedules and other benefits during the review of an advanced reactor license application. This proposal for pre-application activities is essentially a staged licensing approach, where some key elements of an advanced reactor design are reviewed, and the evaluation documented before the license application is submitted. A staged licensing approach has the following advantages:
1 Policy Statement on the Regulation of Advanced Reactors (73 FR 60612; October 14, 2008)
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DRAFT Preapplication Engagement to Optimize Application Reviews Advantages for Applicants Advantages for NRC Enhanced regulatory predictability, reducing Greater review efficiency because NRC staff business risk becomes familiar with design Greater review efficiency because NRC staff Early public engagement on the attributes of becomes familiar with design. Efficiency a design, increasing transparency and translates to lower costs and shorter review enhancing public awareness schedules Regulatory requirements for the design are NRC staff become familiar with unique clarified environmental aspects of a site and new approaches an applicant is considering Early engagement with the Advisory Early engagement with the ACRS through Committee on Reactor Safeguards (ACRS) the review of safety evaluations on topical through the review of safety evaluations on reports. This early ACRS involvement will topical reports. This early ACRS involvement reduce the number of issues addressed will improve regulatory reliability and shorten during the application review and lessen the application review times. effort of application review.
Early interactions between the NRC, the applicant, and other agencies that have a role in the environmental review shorten the licensing review schedule.
Program: As required by NEIMA the NRC staff established generic milestone schedules for licensing reviews2. When the generic milestone schedules were established, the NRC staff noted that it will work with each licensee or applicant to establish a specific schedule for each request, which may be shorter or longer than the generic milestone schedule based on the specific needs of the licensee or applicant and the staff's resources. If an advanced reactor applicant completes the applicable items3 described in the following sections prior to submitting the application, the NRC staff will establish a review schedule at least 6 months shorter than the generic schedules depending on the complexity of the design. The NRC staff will complete the issuance of the final safety evaluation within the established schedule as long as the following conditions are met:
- Applicants must submit responses to requests for additional information (RAIs) and other necessary information within agreed upon milestones. Otherwise the schedule may be adversely affected.
- There can be no substantive changes, other than those resulting from the RAI process, to the application after submittal as they may impact the schedule.
- The design should not change significantly between the pre-application and application so that matters resolved in pre-application are not adversely impacted. Significant design changes would impact the schedule.
2 https://www.nrc.gov/about-nrc/generic-schedules.html 3
For a design certification, only the safety review items would be applicable. For a combined license application referencing a certified design, the environmental review items would be applicable in addition to safety topics associated with site specific features and any departures to the certified design. For a combined license not referencing a certified design, all the review topics listed would be applicable.
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DRAFT Preapplication Engagement to Optimize Application Reviews In addition to a substantially shorter overall application review, staff will complete the acceptance review in two weeks, only addressing administrative aspects including making the application publicly available and issuing notice of availability, if the activities described below are completed before submission of an application.
A. Topical reports The applicant should submit topical reports on key topics for review and approval during the pre-application phase. These reports should be submitted early enough to support staff issuance of final staff safety evaluations prior to submittal of an application. It should be noted that any substantive changes to the design would invalidate the staffs prior approval in these areas and may result in significant changes to the review schedule. The key areas described below should be addressed.
- 1. Principle design criteria4 During the pre-application period, the applicant should submit proposed principal design criteria (PDC) for staff review and approval. As required by 10 CFR 50.34(a)(3)(i), 10 CFR 52.47(a)(3)(i), 10 CFR 52.79(a)(4)(i), proposed PDC must be included in an application for a construction permit (CP), design certification (DC), or combined license (COL). The PDC establish the necessary design, fabrication, construction, testing, and performance of safety significant SSCs. The NRC staff expects prospective non-light-water reactor (non-LWR) applicants will review the GDC pertaining to LWR provided in Appendix A to 10 CFR Part 50 and the guidance in RG 1.232, Guidance for Developing Principal Design Criteria for Non-Light-Water Reactors, to develop their PDC and ensure that necessary safety functions and SSCs are covered under the selected PDC. The staff will review the applicants proposed PDC to determine if they are acceptable.
- 2. Selection of licensing basis events and classification and treatment of structures, systems, and components (SSCs) a) The applicant should request staff review and approval of their proposed process for selection of licensing basis events and classification and treatment of SSCs or indicate that they plan to use an approved existing process such as the process described in Regulatory Guide 1.233, Guidance for a Technology-Inclusive, Risk-Informed, and Performance-Based Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light-Water Reactors.
b) The applicant should also submit for NRC information the anticipated list of licensing basis events and the associated list of safety related and risk significant 4
Prospective applicant for small modular light-water reactor (SMR) designs are not required to submit PDC. SMR developers should instead discuss how the general design criteria (GDC) in Appendix A to 10 CFR Part 50 will be applied to their design and discuss any proposed exemptions to the GDC.
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DRAFT Preapplication Engagement to Optimize Application Reviews SSCs. This will help the staff understand the design and would support discussions on the preliminary SSC classifications, as needed, in preparation for an efficient and effective application review.
- 3. Fuel qualification and testing Applicants need to develop and execute fuel qualification plans that include fuel testing and validation and verification of associated engineering computer programs.
The qualification plan needs to include fuel performance methodology and application. The applicant should submit the fuel qualification plan and associated methodologies to the NRC staff for review and approval. Preapplication engagement on fuel qualification should include the following steps: staff approval of the fuel qualification plan and associated methodologies, potential staff observation of execution of the testing, and verification of the results (via topical report or an audit) of the testing to support qualification of the fuel for the associated reactor design.
- 4. Mechanistic or accident source term development5 Applicants need to develop a source term methodology that includes validation and verification of associated engineering computer programs. The source term development needs to include radiological source terms for effluents, radwaste system design, shielding design and equipment qualification. The applicant should submit the source term methodologies to the NRC staff for review and approval.
- 5. Quality assurance program Applicants should submit a quality assurance program description (QAPD) for NRC review and approval during the pre-application phase to ensure that the design and the application have been developed in accordance with 10 CFR Part 50 Appendix B. The QAPD should cover the scope of the planned type of license application (e.g., 10 CFR 52.47(a)(19) discusses the QAP requirements for DC applications and 10 CFR 52.79(a)(25) discusses the QAP requirements for COL applications) as applied to the fabrication, construction, and testing, of the SSCs of the facility. The description of the QAP must include a discussion of how the applicable requirements of Appendix B to 10 CFR part 50 have been and will be satisfied, including a discussion of how the QAP will be implemented.
- 6. Safeguards Information Plan The applicant should submit a plan for the protection of safeguards information (SGI) for NRC review and approval during the preapplication period to enable the NRC staff to provide the applicant with SGI information, as necessary, for the applicant to consider safeguards and security into the design of the facility and the physical security program in order for the applicant to address the requirements of 10 CFR Part 73, Physical Protection of Plants and Materials, and 10 CFR 50.150, Aircraft impact assessment, in their application.
- 7. Safety and accident analysis methodologies and associated validation 5
SMR developers may use the accident source term in NUREG-1465, Accident Source Terms for Light-Water Nuclear Power Plants, or propose a design specific accident source term.
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DRAFT Preapplication Engagement to Optimize Application Reviews Applicants need to develop and execute plans to perform safety and accident analyses that include testing of applicable SSCs and validation and verification of associated engineering computer programs. The analysis plans need to include development of associated methodologies and applications of those methods which include but are not limited to event specific analysis methodologies, scaling methodology, setpoint methodology, reactor coolant analysis methodology, core design methodology, and reactivity control methods. The analysis plans need to include a test plan and test program as well as equipment qualification methodology to ensure appropriate verification and validation of the engineering computer programs. The applicant should submit the safety analysis methodologies and application of those methods to the NRC staff for review and approval.
B. Meetings, audits and white papers:
In addition to the topical reports discussed above, applicants should engage in pre-application interactions on the following key topics:
Applicants should allow the NRC staff to audit the preliminary PRA and PRA peer review prior to submitting an application. The PRA will likely play an important role in the selection of licensing basis events and classification and treatment of SSCs, so early feedback on the PRA can avoid delays during the application review. The applicant needs to explain how the PRA will be used to support their application (risk informed licensing, event selection for siting and emergency preparedness, maintenance rule, etc.) to determine acceptability of the PRA for its planned use.
The staff will audit resolution of the peer review observations and findings. The staff will assess the acceptability of the PRA for its proposed uses and the applicant must address any issues identified before submittal of the application.
- 2. Regulatory Exemptions Applicants may request exemptions from the NRCs regulations on a case-by-case basis. The applicant should submit a white paper providing a regulatory gap analysis listing the areas where the applicant plans to request exemptions from NRC requirements. This would allow the staff and the applicant to establish the list of the regulations that are applicable to the design to support an efficient acceptance review. It would also allow the NRC and the applicant to establish a path forward for reviewing proposed exemption requests. Examples of potential exemption requests may include emergency planning zone size and number of armed responders for physical security in advance of completion of ongoing rulemakings.
- 3. Policy issues The wide spectrum of designs and/or design features being contemplated by advanced reactor designers may present unique policy issues. These policy issues need to be brought forward, through white papers or meetings, to the NRC staff as early as possible so that they can be properly considered and addressed by the NRC Page 5 of 9
DRAFT Preapplication Engagement to Optimize Application Reviews before the application is submitted. If additional policy issues arise during the application review, the schedule may be impacted.
- 4. Novel design features or approaches The applicant should identify any novel design features, through white papers or meetings, during the pre-application review to allow staff familiarization so staff can develop review strategy and review guidance, if needed. If the applicant intends to use novel design features (such as passive systems, inherent safety features, or simplified control features), early identification of these features or approaches to the NRC staff will facilitate timely identification and resolution of any unique regulatory topics. Topics to be considered beyond the reactor system include unique features such as seismic isolators, novel digital instrumentation and control systems, security features, or novel approaches to operational programs.
- 5. Consensus codes and standards and code cases During the pre-application stage the applicant should use a white paper to identify any consensus codes and standards or code cases they intend to use and specifically identify any standards or code cases that have not been endorsed or previously accepted by the staff. For any such standards or code cases, the applicant should engage in pre-application discussions to identify any areas where additional information may be needed in the application to support the proposed approach.
- 6. Identification and justification of the use of engineering computer programs used in the application The applicant should submit a white paper describing the anticipated list of the engineering computer codes and intended application during the pre-application phase. The validation and acceptability basis should be described as well as background and historical acceptance.
- 7. Pre-application Readiness Assessment In addition to the above pre-application activities, the applicant should allow the staff to conduct a pre-application readiness assessment (see Office instruction LIC-116, Pre-application Readiness Assessment, ADAMS Accession No. ML20104B698) of both safety and environmental topics. The readiness assessment would allow the NRC staff to: (1) identify information gaps between the draft application and the technical content expected to be included in the final application submitted to the NRC, (2) identify major technical and/or policy issues not previously identified that may adversely impact the docketing or technical review of the application, and (3) become familiar with the application, particularly in areas where prospective applicants are proposing new concepts or novel design features not previously identified. The results of the readiness assessment will inform prospective applicants in finalizing their application and assist the NRC staff in planning its resources for the review once the application is formally submitted. The staff plans to engage prospective applicants to schedule a pre-application readiness assessment at least 6 months prior to the expected date of submittal. The readiness assessment is not part of the NRCs official acceptance review process and does not predetermine whether Page 6 of 9
DRAFT Preapplication Engagement to Optimize Application Reviews the application will be docketed. An applicant should provide the most current draft of the environmental report, referenced documentation, and applicant staff and contractors to assist the NRC staff during its readiness assessment.
C. Environmental Activities As a Federal agency, the NRC follows National Environmental Policy Act requirements to assess the environmental effects of proposed actions prior to making decisions.
Therefore, the environmental review is an integral but distinct part of the NRCs licensing review.
Early and frequent pre-application interactions is a key component of federal directives outlined in FAST-41 and Executive Order 13807 to streamline the environmental review process. As such, the staff expects that applicants would conduct meetings, support audits, and provide white papers during pre-application activities that would occur approximately 2 years in advance of the application submittal. An applicant seeking a predictable review schedule should engage in substantive pre-application interactions with the NRC staff as early as possible in the planning process before submitting environmental information or filing an application in accordance with 10 CFR 51.40, Consultation with NRC staff, and as discussed in Regulatory Guide (RG) 1.206, Combined License Applications for Nuclear Power Plants. In addition, an applicant is expected to address the environmental issues described in RG 4.2, Preparation of Environmental Reports for Nuclear Power Stations, which provides guidance to applicants for the format and content of environmental reports (ERs) that are submitted as part of an application for a permit, license, or other authorization to site, construct, and/or operate a new nuclear power plant, or provide a justification for any issues that do not need to be analyzed. In addition, an applicant should also consider following the guidance in NEI 10-07, Industry Guideline for Effective Pre-Application Interactions with Agencies Other Than NRC During the Early Site Permit Process, and consider COL Interim Staff Guidance (ISG)-29, Environmental Considerations Associated with Micro-reactors.
White Papers The applicant should submit white papers on key and novel approaches to environmental topics for staff assessment and feedback during the pre-application phase. These reports should be submitted early enough to gain alignment with NRC staff, and if needed the applicant will support meetings or audits regarding the information presented in the white papers. The following key areas should be addressed in white papers and discussed with staff as needed to ensure staff understanding of the proposed methodology.
- 1. Unique or Novel Methodologies and Issues The applicant should identify (in consultation with the staff if needed) any novel environmental methodology that has not previously been analyzed by the staff during the pre-application to allow staff familiarization so staff can develop review strategy and review guidance, if needed. An example of a unique issue would be unique purpose and need for the project such as uses other than electricity production. Because the purpose and need statement determines the scope of Page 7 of 9
DRAFT Preapplication Engagement to Optimize Application Reviews the alternatives for the project, it is important to have early alignment with the staff.
- 2. Alternatives to the Proposed Project A recurring issue on many of the previous COLs was the alternative site selection process. The applicant should present white papers and support meetings to discuss the site selection process. In addition, a unique issue for advanced reactors could be energy alternatives, depending on the electrical output of the facility, which could bring into the alternative analysis renewable energy sources previously not considered for large LWRs.
- 3. Cooling Water Availability The staff understands that for advanced reactors the use of cooling water would likely be less than that of large LWRs; however, the necessary approvals by the permitting authorities for access to cooling water proved to be a challenge for many sites. Therefore, the staff expects an applicant to provide the necessary information on water consumption for the proposed facility and periodic status of obtaining the necessary permits. The staff also recommends that the applicant, the NRC staff, and the water permitting agencies meet at least once during the pre-application activities.
- 4. Status of Permits and Authorizations for the Proposed Project The staff recommends that the applicant interact with other permitting agencies as discussed in NEI 10-07, Industry Guideline for Effective Pre- Application Interactions With Agencies Other Than NRC During the Early Site Permit Process, and provide a list of the needed authorizations, permits, licenses, and approvals for the project. This documentation should also contain a timeline for obtaining the necessary permits and the current status. The applicant should also provide copies of available correspondence between the applicant and State Historic Preservation Office (SHPO), Tribes, U.S. Fishery and Wildlife Service (FWS), U.S. Army Corps of Engineers, National Marine Fisheries Service (NMFS), state and local officials.
Meetings and Audits The staff expects the following topics to be discussed at meetings or audits during pre-application interactions:
- Information on socioeconomics characteristics of the community
- Aquatic or terrestrial ecology studies that have been performed (if any).
- Federally listed species and critical habitats present, and potential impacts on those species and habitats
- Potential impacts on Essential Fish Habitat, including prey of Federally managed species.
- Identify historic properties and other cultural resources within the direct and indirect areas of potential effect (APE). Summarize cultural resource investigations conducted in the APE (all past and current historic and cultural resource investigations), and outreach conducted with the SHPO, Page 8 of 9
DRAFT Preapplication Engagement to Optimize Application Reviews Tribal Historic Preservation Officer, American Indian Tribes, and interested parties.
- Discussion of severe accident mitigation analysis that uses the latest update to the plants probabilistic risk assessment.
- Description of the fuel cycle and its impacts as related to the reactor design including the management of spent nuclear fuel.
- Discussion of the environmental impacts from the transportation of fuels and wastes.
- Design-specific information needed for the environmental review including:
- radiological health impacts (10 CFR Part 20 exposure analysis, annual population dose, non-human biota dose),
- radiological waste management including effluent releases and solid wastes, as applicable,
- non-radiological waste management, and
- postulated accidents and severe accident mitigation alternatives, as applicable.
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