Document: NUREG-0800
Document ID: bc88943d-7cf4-4d62-9d52-975e4cc5d7f9
Document Type: srp
Title: square kilometers (mile)  averaged over any radial distance out to 48.3 kilometers
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070219.pdf
Revision Date: 2023-06
Chapter: 2
Section ID: 2.59
CFR Part: 
CFR Title: 

Content:
e site, including transients. 2.1.3-7 DRAFT Rev. 3 - April 1996 The Emergency Preparedness Licensing BranchEmergency Preparedness and Radiation Protection Branch shall determine that: 43 The applicant also has calculated the radiological consequences of design basis accidents at the outer boundary of the low population zone (SRP Section Chapter 15) and has 44 provided reasonable assurance that appropriate protective measures can be taken within the low population zone to protect the population in the event of a radiological emergency. For design certification reviews, the findings will also summarize, to the extent that the review is not discussed in other safety evaluation report sections, the staff’s evaluation of inspections, tests, analyses, and acceptance criteria (ITAAC), including design acceptance criteria (DAC), site interface requirements, and combined license action items that are relevant to this SRP section.45 V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans for using this SRP section. This SRP section will be used by the staff when performing safety evaluations of license applications submitted by applicants pursuant to 10 CFR 50 or 10 CFR 52. Except in those 46 cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described herein will be used by the staff in its evaluation of conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications docketed six months or more after the date of issuance of this SRP section.47 Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guides and NUREGs. VI. REFERENCES 1. 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities." 2. 10 CFR Part 100, "Reactor Site Criteria." 3. Regulatory Guide 1.70, "Standard