Document: NRC Regulatory Guide
Document ID: b143ccef-ed08-482d-bc4b-b4e012328090
Document Type: regulatory_guide
Title: Applications for Nuclear Power Plants (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1523/ML15233A056.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.206
CFR Part: 
CFR Title: 

Content:
that has been finalized to the point that procurement specifications and construction and installation specifications can be completed and made available for audit if such information is necessary for the Commission to make its safety determination. The Statement of Consideration further states that how much detail is present in a DC will be an issue which will have to be resolved in each certification rulemaking but that a rule certifying a design is likely to encompass roughly the same design features that 10 CFR 50.59 prohibits changing without prior NRC approval. The Commission established policy in its February 15, 1991, SRM for SECY-90-377 (Ref. 86). Section III, “Level of Detail,” of SRM-SECY-90-377 addresses the expected level of detail in DC applications. Specifically, the design should be complete except for adjustment within established design envelopes during the procurement and installation process. The Commission, however, did not expect in all instances that design detail would be developed to the level found in actual procurement and construction specifications, thus affording some flexibility to accommodate as-procured characteristics. In SRM-SECY-90-377, the Commission approved the NRC staff’s proposal for a graded approach to the level of needed design detail, reflecting the safety significance of the SSC. The Commission considered an appropriate level of detail to be that provided in the FSAR at the operating license stage for a recently licensed plant (except for site-specific, as-procured, and as-built information). DG-1325, Page-65 SECY-92-053, “Use of Design Acceptance Criteria during 10 CFR Part 52 Design Certification Reviews,” dated February 19, 1992, (Ref. 87), describes topics for which the design could not be completed to the level of detail originally envisioned in SECY-90-377 and its associated SRM. Instead, the NRC staff defined DAC as a set of prescribed limits, parameters, procedures, and attributes that it relies on in a