Document: NRC Regulatory Guide
Document ID: f0baf50b-5bb7-4783-b2f9-9586e09c97e1
Document Type: regulatory_guide
Title: Preparation of Environmental Reports for Nuclear Power Stations + HISTORY - HISTORY 02/2017 – DG-4026 , Proposed Revision 3 09/2014 – Periodic Review of Revision 2 – Revise (Rev. 3)
Source: NRC Regulatory Guide Division 4
Source URL: https://www.nrc.gov/docs/ML1611/ML16116A068.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-4.2
CFR Part: 
CFR Title: 

Content:
analysis of transportation impacts should include the following: • Transportation of unirradiated fuel. The analysis should include the radiological impacts associated with the normal conditions of transport and the nonradiological impacts associated with transportation accidents. • Transportation of irradiated fuel. The analysis should include the radiological impacts associated with the normal conditions of transport and the radiological and nonradiological impacts associated with transportation accidents. • Transportation of radioactive waste. The analysis should include the radiological impacts associated with the normal conditions of transport and the nonradiological impacts associated with transportation accidents. The transportation impacts analysis should use the latest versions of transportation computer codes. For example, SAND2013–8095, “RADTRAN 6/RadCat 6 User Guide” (Ref. 86), and ORNL/NTRC-006, Revision 0, “Transportation Routing Analysis Geographic Information System (TRAGIS) User’s Manual” (Ref. 87).The following data should be provided in the ER: • reactor type and rated core thermal power • fuel assembly description 15 Regulations in 10 CFR 51.52(a)(2) specify the use of zircaloy as the fuel rod cladding material. The NRC has also specified in 10 CFR 50.46 that ZIRLO™ is an acceptable fuel rod cladding material, and that with regard to the potential environmental impacts associated with the transportation of the M5® clad fuel assemblies, the M5® cladding has no impact on previous assessments determined in accordance with 10 CFR 51.52 (65 FR 794). DG-4.2, Page 118 • average irradiation level of irradiated fuel • the capacity of the onsite storage facilities to store irradiated fuel and the minimum fuel storage time between removal from the reactor and transportation offsite • treatment and packaging procedures for radioactive wastes other than irradiated fuel • general description of transportation packaging