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:
etail 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 include FSAR pages and technical specifications. Licensees should submit affected FSAR pages and technical specifications annotated with changes that reflect the revised analyses. Additionally, the NRC staff recommends that licensees submit the actual calculation documentation. In lieu of submitting marked up FSAR pages, licensees should include a detailed listing, preferably in tabular format, of all changes and associated justification being proposed between the current facility licensing basis and the requested license amendment. If the licensee has used a current approved version of an NRC-sponsored computer code, the NRC staff review can be made more efficient if the licensee identifies the code used and submits the inputs that the licensee used in the calculations made with that code. In many cases, this information will 8 The analyses required by 10 CFR 50.67 are important to the design basis of the facility, and 10 CFR 50.34 requires design basis safety analyses and evaluations; they are a significant input to the evaluations required by 10 CFR 50.92, “Issuance of Amendment,” or 10 CFR 50.59. DG-1389, Page 16 help support efficiency in the NRC staff’s review and confirmatory analyses. This recommendation does not constitute a requirement that the licensee use NRC-sponsored computer codes. Applications for licenses, certifications, and approvals under 10 CFR Part 52 have requirements similar to those stated above for license amendment submittals. RG 1.206, “Applications for Nuclear Power Plants (LWR Edition),” issued October 2018 (Ref. 23), provides additional guidance on combined license applications. 1.6 Final Safety Analysis Report Requirements The regulations in 10 CFR 50.71, “Maintenance of Records, Making of Reports,” include the requirements