Document: NUREG-1555
Document ID: 487de72c-0092-45b4-a6e4-6e5f7ca7ad74
Document Type: esrp
Title: TRANSPORTATION OF RADIOACTIVE MATERIALS
Source: NUREG-1555
Source URL: https://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1555/initial/
Revision Date: 2007-10
Chapter: 3
Section ID: 3.8
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Content:
REVIEW RESPONSIBILITIES Primary—Appendix B Secondary—Appendix B I. AREAS OF REVIEW This environmental standard review plan (ESRP) directs the staff’s review and analysis of the proposed means of transporting radioactive materials. The scope of the review directed by this plan will be limited to those design and operational parameters specified in 10 CFR 51.52(a). Review Interfaces The reviewer for this ESRP should obtain input from or provide input to the reviewers for the following ESRPs, as indicated: ` ESRP 3.2. Obtain input on the reactor type and rated core thermal power, the fuel assembly descrip- tion, and the average irradiation level of irradiated fuel. ` ESRP 5.4.2. Provide the reviewer for ESRP 5.4.2 with a description of the transportation of radioactive materials and an evaluation of transportation relative to the criteria associated with Table S-4 of 10 CFR 51.52(c). If an independent analysis of the impacts of transportation is required, ensure that sufficient information to support an independent analysis of these impacts is provided. NUREG-1555 3.8-2 October 1999 ` ESRP 7.4. Provide the reviewer for ESRP 7.4 with a description of postulated accidents associated with transportation of radioactive materials and an evaluation of the transport relative to the criteria associated with Table S-4 of 10 CFR 51.52(c). If an independent analysis of the impacts of transportation accidents is required, ensure that sufficient information to support an independent analysis of these impacts is provided. Data and Information Needs The type of data and information needed will be affected by site- and station-specific factors, and the degree of detail should be modified according to the anticipated magnitude of the potential impacts. The following data or information should be obtained: ` reactor type and rated core thermal power (from ESRP 3.2) ` fuel assembly description (from ESRP 3.2) ` average irradiation level of irradiated fuel (from ESRP 3.2) ` the