Document: NUREG-0800
Document ID: c75a9de4-9927-49e4-b078-7f5dadd37acd
Document Type: srp
Title: DESIGN BASIS ACCIDENT RADIOLOGICAL CONSEQUENCE ANALYSES FOR
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0702/ML070230012.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.0.3
CFR Part: 
CFR Title: 

Content:
ical rationale for application of these acceptance criteria to the areas of review addressed by this SRP section is discussed in the following paragraphs: 1. Compliance with 10 CFR 50.34(a)(1) ensures that the safety analysis report (SAR) includes a description and safety assessment of the standard design, custom design 15.0.3-8 March 2007 and/or site on which the facility is to be located. The review performed under this SRP section ensures that the SAR contains a sufficient description of the design basis accident radiological consequences analyses that will enable the staff to evaluate the planned site and provide reasonable assurance that plant design and operation will reflect site considerations in a manner adequate to minimize the consequences of an accident. The dose acceptance criteria in Table 1 of this SRP section are fractions of the 10 CFR 50.34(a)(1) dose reference values for accidents other than the LOCA, as has been done historically. For events having a moderate frequency of occurrence, any release of radioactive material must be such that the calculated offsite doses are a small fraction of the 10 CFR 50.34(a)(1) reference values. A small fraction is defined as less than 10% of the 10 CFR 50.34(a)(1) reference values, or 2.5 rem TEDE. The plant site and dose mitigating engineered safety features are acceptable with respect to the radiological consequences of a postulated control rod drop accident (BWR), control rod ejection accident (PWR), fuel handling accident or cask drop accident if the calculated offsite doses are well within the dose reference values in 10 CFR 50.34(a)(1). “Well within" is defined as 25% of the 10 CFR 50.34(a)(1) reference values, or 6.3 rem TEDE. 2. Compliance with the radiological provision of GDC 19 provides assurance that control of the plant is maintained during emergency operation. The applicant is required to maintain the control room in a safe condition under accident conditions, including loss-of- coolant