Document: NUREG-0800
Document ID: 35d16973-484d-41cb-9b6c-d66cae8072ca
Document Type: srp
Title: EMERGENCY PLANNING
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0634/ML063410307.pdf
Revision Date: 2023-06
Chapter: 13
Section ID: 13.3
CFR Part: 
CFR Title: 

Content:
reactor site, and the application proposes to incorporate and extend elements of the existing emergency planning program to the new reactor (including by reference), those existing elements should be considered acceptable and adequate. The reviewer will generally focus the review on the extension of the existing program to the new reactor, and will determine whether the incorporated emergency planning program information from the existing reactor site (1) is applicable to the proposed reactor, (2) is up-to-date when the application is submitted, and (3) reflects use of the site for construction of a new reactor (or reactors) and appropriately incorporates the new reactor(s) into the existing plan. The safety evaluation report (SER) should document the bases for concluding that included (or referenced) information from an existing emergency preparedness program satisfies the applicable acceptance criteria. The reviewer will also examine how the existing elements are incorporated into the application, determine the acceptability of expanding the existing program to include one or more additional reactors, and determine the acceptability of the applicant’s identification of any impact on the adequacy of the existing emergency preparedness program for the operating reactor (or reactors). The reviewer will confirm that the applicant has appropriately identified whether any updates are required to existing emergency facilities and equipment, including the Alert and Notification System (ANS), in order to accommodate extension to the proposed new reactor. If appropriate, the reviewer will determine whether the applicant has addressed the exercise requirements for co-located licensees, in accordance with Section IV.F.2.c of Appendix E to 10 CFR Part 50, and the conduct of emergency preparedness activities and interactions discussed in Regulatory Guide 1.101, Rev. 5. For all reactor license applications (excluding standard design certifications), submitted pursuant to 10