§ 53.1239 Contents of applications for standard design certifications; technical information.
The application must contain a level of design information sufficient to enable the Commission to judge the applicant's proposed means of assuring that construction conforms to the design and to reach a final conclusion on all safety questions associated with the design before the certification is granted. The information submitted for a design certification must include performance requirements and design information sufficiently detailed to permit the preparation of acceptance and inspection requirements by the NRC. The Commission will require, before design certification, that information normally contained in engineering documents, such as analyses, drawings, procurement specifications, or construction and installation specifications, be completed and available for audit if the more detailed information is necessary for the Commission to verify the information in the application and make its safety determination.
(a) Final Safety Analysis Report. The application must contain an FSAR that describes the facility and the limits on its operation, and presents a safety analysis of the SSCs, and must include the following information:
(1) Site parameters. The site parameters postulated for the design under this part, including the design-basis external hazard levels for the relevant external hazards, and an analysis and evaluation of the design in terms of those site parameters.
(2) Plant description and safety functions—(i) General plant description. A general description of the commercial nuclear plant including reactor type, the intended use of the reactor, nuclear design (e.g., neutron spectrum, reactor control, multi-unit reactor control), overall layout of the plant including significant plant features and SSCs, maximum power level and the nature and inventory of radioactive materials.
(ii) Safety functions. A description of the primary and additional safety functions required under § 53.230 and a summary of how each safety function is satisfied.
(3) Design features and functional design criteria—licensing-basis events. (i) A description of the design features required by § 53.400 and the functional design criteria required by §§ 53.410 and 53.420 that, when combined with corresponding human actions and programmatic controls, demonstrate that the plant will demonstrate compliance with the safety criteria defined in § 53.210 and established in accordance with § 53.220 during licensing-basis events (LBEs).
(ii) A description of how design features demonstrate compliance with the requirements of § 53.440(a) through (i) and (k) through (m).
(4) Design features supporting normal operations. A description of the design features required by § 53.425 to support the holder of an OL or COL complying with § 53.260 during normal operations.
(5) [Reserved]
(6) Earthquake engineering. The information necessary to demonstrate that the commercial nuclear plant complies with the earthquake engineering criteria in § 53.480.
(7) Programmatic controls and interfaces. (i) A description of the corresponding programmatic controls and interfaces necessary to achieve and maintain the reliability and capability of SSCs relied upon to demonstrate compliance with the functional design criteria required by §§ 53.410 and 53.420 and the safety criteria in §§ 53.210 and 53.220 and necessary to maintain consistency with analyses required by § 53.450.
(ii) For an application for a multi-unit commercial nuclear plant, the programmatic controls and interfaces must also be described for different modular configurations, as required by § 53.440(i), including any restrictions that will be necessary during the construction and startup of any given unit to ensure the safe operation of the overall commercial nuclear plant to be licensed under this part.
(8) Programmatic controls for normal operations. A description of how programmatic controls, including monitoring programs, would provide assurance that design features and procedures will enable the holder of an OL or COL to comply with § 53.260.
(9) Design features supporting the protection of plant workers. A description of the design features required by § 53.430 to support the holder of an OL or COL complying with § 53.270.
(10) Programmatic controls for protection of plant workers. A description of how programmatic controls, including monitoring programs, would provide assurance that design features and procedures will enable the holder of an OL or COL to comply with § 53.270.
(11) Codes and standards. A description of generally accepted consensus codes and standards used to design the design features, as required by § 53.440(b).
(12) Materials. A description of the materials used for SR and NSRSS SSCs and a description of the qualification of these materials for their service conditions over the plant lifetime, as required by § 53.440(c).
(13) Integrity assessment program. A description of a design integrity assessment program that addresses the elements described in § 53.440(d).
(14) [Reserved]
(15) Criticality. Information demonstrating how the applicant will comply with requirements for criticality accidents in § 53.440(m).
(16) Multi-unit plants. For an application for standard design certification of a multi-unit commercial nuclear plant, the possible operating configurations of the reactor units, including common systems, interface requirements, and system interactions, as required by § 53.440(i).
(17) SSC classification. (i) The classification of SSCs according to their safety significance under § 53.460(a).
(ii) For SR and NSRSS SSCs, the conditions under which they must perform the safety functions required by § 53.230, including environmental conditions.
(18) Probabilistic risk assessment or other systematic risk evaluations (SREs). A description of the probabilistic risk assessment (PRA), other SREs, or a combination thereof required by § 53.450(a) and associated results.
(19) Analyses. A description of the analyses performed under § 53.450(b) through (g) that includes the following information:
(i) A description of the analysis of LBEs and its results, as described in § 53.240. This analysis description must—
(A) Address the elements in § 53.450(e) and (f); and
(B) Under § 53.460(c)—
(1) Describe any human actions that are necessary to prevent or mitigate LBEs;
(2) Describe how those human actions are capable of being reliably performed under the postulated environmental conditions present; and
(3) Describe how those human actions would be addressed by programs established under subpart F of this part.
(ii)(A) A description of how SSCs relied on to meet the safety criteria defined in § 53.210 are protected against or designed to withstand the effects of external hazards under § 53.510.
(B) The information necessary to demonstrate that the commercial nuclear plant complies with the earthquake engineering criteria in § 53.480.
(iii) A description of the defense-in-depth measures required by § 53.250.
(iv) A description of all plant operating states where there is the potential for the uncontrolled release of radioactive material to the environment, as required by § 53.450(b)(4).
(v) A description of the events that challenge plant control and safety systems whose failure could lead to an undesirable end state and/or radioactive material release, as required by § 53.450(b)(5).
(vi) A description of the analytical codes used in modeling plant behavior in analyses of LBEs and how these codes are qualified for the range of conditions for which they were used, as required by § 53.450(d).
(vii) A description of the results of other analyses required by § 53.450(g).
(20) Special treatments. A description of special treatments established as required by § 53.460.
(21) [Reserved]
(22) Quality assurance. A description of the QAP applied to the design of the SSCs of the commercial nuclear plant, as required by § 53.460(b). The description of the QAP for a commercial nuclear plant must include a discussion of how the applicable requirements of appendix B to part 50 of this chapter were satisfied.
(23) Design features and controls to address the minimization of contamination. The information required by § 20.1406 of this chapter.
(24) Interface requirements. (i) A description analysis, and evaluation of the interfaces between the standard design and the balance of the commercial nuclear plant that may impact the ability of the plant to demonstrate compliance with the functional design criteria or the safety criteria of subparts B and C of this part.
(ii) Confirmation that interface requirements are verifiable through inspections, testing, or analysis. These requirements must be sufficiently detailed to allow for completion of the final safety analysis by license applicants that reference the certified design under this subpart. The method to be used for verification of interface requirements must be included as part of the proposed ITAAC required by § 53.1241(a)(3).
(iii) A representative conceptual design for those portions of the plant for which the application does not seek certification to aid the NRC in its review of the FSAR and to permit assessment of the adequacy of the interface requirements under paragraph (a)(24)(i) of this section.
(25) Technical qualifications. A description of the technical qualifications of the applicant to engage in the proposed activities in accordance with the regulations in this chapter.
(26) Technical specifications. Proposed technical specifications prepared under § 53.710(a) for those areas addressed by the design certification.
(27) Role of personnel. Information to address the following for the role of personnel in ensuring safe operations:
(i) A description of how the human factors engineering design requirements of § 53.440(n)(1) are addressed;
(ii) A description of how the human system interface design requirements of § 53.440(n)(2) are addressed;
(iii) A concept of operations that is of sufficient scope and detail to address the requirements of § 53.440(n)(3);
(iv) A functional requirements analysis and function allocation that is of sufficient scope and detail to address the requirements of § 53.440(n)(4).
(b) [Reserved]