Document: NRC Regulatory Guide
Document ID: 5810150e-ee20-4cd1-b72f-6e918a603f73
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:
RP acceptance criteria. The SSAR is similar in format to a COL FSAR. The SSAR content includes detailed site-specific characteristics and the potential reactor facility information that applies to the issuance of an ESP. An ESP that is issued prior to selection of a reactor design will follow the plant perimeter envelope (PPE) approach which establishes postulated values of design parameters that provide design details to support the NRC staff’s review of an ESP application. A controlling PPE value, or bounding parameter value, is one that necessarily controls the value of a site characteristic. As the PPE is intended to bound multiple reactor designs, the actual design selected in a COLA referencing an ESP must fit within the bounding parameter values. As illustrated in Table 2, the SSAR contains a subset of the chapters in a COL FSAR. The following summarizes the scope of the SSAR chapters: a. Chapter 1 is analogous to a COL FSAR for the potential future facility and reactor designs. b. Chapter 2 is analogous to a COL FSAR. For an ESP that uses a plant parameter envelope (PPE) instead of specific reactor facility information, the PPE is given here. c. Chapter 3 is limited to Section 3.5 on aircraft hazards. d. Chapter 11 is limited to addressing whether effluent releases and public dose limits can be met for the site. e. Chapter 12 is limited to addressing doses to construction workers, especially from onsite sources of direct radiation, and possible direct dose contributors to offsite members of the public. f. Chapter 13 is limited to Section 13.3 on emergency planning (EP) and Section 13.6 on site characteristics for adequate security planning. g. Chapter 14 is optional and addresses ITAAC that apply to EP or an LWA. h. Chapter 15 is analogous to a COL FSAR for the potential reactor designs but is limited to Section 15.0.3 addressing the evaluation of the radiological consequences of design basis accidents. i. Chapter 17 is analogous to a COL FSAR but