Document: NRC Regulatory Guide
Document ID: 4d46a966-d280-43da-9b03-8b0abe7b29ce
Document Type: regulatory_guide
Title: Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2120/ML21204A065.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.183
CFR Part: 
CFR Title: 

Content:
red and should follow, as far as applicable, the form prescribed for original applications. RG 1.70, Revision 3, “Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants (LWR Edition),” issued November 1978 (Ref. 22), provides additional guidance. Per 10 CFR 50.67, “[t]he NRC may issue the amendment only if the applicant’s analysis demonstrates with reasonable assurance that” the identified dose criteria are met. The licensee’s analyses that will become part of the design and licensing basis of the facility are, therefore, key aspects of the submittal information. This information submitted in the amendment request, along with the current plant design as documented in the FSAR, staff safety evaluation reports, regulatory guidance, other licensee commitments, and staff experience gained in approving similar requests for other plants also provide important information. The methods and analysis described in this guidance are acceptable to the NRC staff for meeting the requirements in 10 CFR 50.67. However, if licensees propose to use alternatives different from this guidance, licensees should provide sufficient justification to demonstrate the requirements for the pertinent regulations are satisfied. Importantly, as noted above, per 10 CFR 50.67, the amendment may only be issued “if the applicant’s analysis demonstrates with reasonable assurance” that the identified dose criteria are met, and therefore, licensees should ensure that adequate information, such as analysis assumptions, inputs, and methods, is presented in the submittal to support the staff’s assessment.8 The amendment request should describe the licensee’s analyses of the radiological and non- radiological impacts of the proposed modification in sufficient detail to support review by the NRC staff. Consistent with 10 CFR 50.90, the licensee shall, as far as applicable, follow the form prescribed for original applications. Typically, original applications