Document: NUREG-0800
Document ID: 23a67737-6e7e-4dfc-9090-dca6a186a7dc
Document Type: srp
Title: RADIOLOGICAL CONSEQUENCES OF MAIN STEAM LINE FAILURES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070679.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.1.5
CFR Part: 
CFR Title: 

Content:
rates so that potential offsite doses are small. At the operating license stage, we will include appropriate limits on these parameters to be included in the plant technical specifications. 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.44 V. IMPLEMENTATION The following provides guidance to applicants and licensees regarding the 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 45 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.46 Implementation schedules for conformance to parts of the method described herein are contained in the referenced regulatory guide. VI. REFERENCES 1. 10 CFR 100.11,Part 100, Section 11, "Determination of Exclusion Area, 47 Low Population Zone, and Population Center Distance." DRAFT Rev. 3 - April 1996 15.1.5-8 2. Standard Technical Specifications for Combustion Engineering PWRs, NUREG-02121430.48 3. Standard Technical Specifications for Westinghouse PWRs, NUREG-04521431.49 4. Standard Technical Specifications for Babcock and Wilcox PWRs, NUREG-01031432.50 5 NUREG-1465, "Accident Source Terms for Light-Water Nuclear Power Plants," February 1995.51 56. R. R. Bellamy, "A Regulatory