Document: NRC Regulatory Guide
Document ID: 769c53ca-7692-4fdf-9301-9fd64e37aa8f
Document Type: regulatory_guide
Title: Evaluations of Explosions Postulated To Occur on Transportation Routes Near Nuclear Power Plants (Rev. 3)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2110/ML21105A439.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.91
CFR Part: 
CFR Title: 

Content:
-0011, 3150-0151 and 3150-0093, respectively. Send comments regarding this information collection to the Freedom of Information Act (FOIA), Library, and Information Collections Branch ((T6-A10M), U.S. Nuclear Regulatory Commission, Washington, DC 20555 0001, or by e-mail to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202 (3150-0011, 3150-0151 and 3150-0093) Office of Management and Budget, Washington, DC, 20503. Public Protection Notification The NRC may not conduct or sponsor, and a person is not required to respond to, a collection of information unless the document requesting or requiring the collection displays a currently valid OMB control number. DG-1388, Page 4 B. DISCUSSION Reason for Revision RG 1.91 “Evaluations of Explosions Postulated to Occur on Transportation Routes near Nuclear Power Plants,” Revision 2, was issued in April 2013. The NRC issued an expert evaluation team report, “Report of the U.S. Nuclear Regulatory Commission Expert Evaluation Team on Concerns Pertaining to Gas Transmission Lines Near the Indian Point Nuclear Power Plant,” (Ref.5) in April 2020 which identified several recommendations with respect to updates to RG 1.91, Revision 2. In response, this revised guide addresses those recommendations without endorsing any particular methodology or set of assumptions. It includes references to pertinent information and methodologies as available. The applicant or licensee, at their discretion, can use other methodologies and assumptions in meeting the NRC regulations and acceptance criteria. This revised guide, therefore, reflects updates based on the recommendations of the expert evaluation team report and presents information pertinent to addressing current NRC methodologies, as appropriate. Background To meet GDC 4 of Appendix A to 10 CFR Part 50 regarding dynamic effects, the SSCs important to safety of a nuclear power plant must be appropriately protected against