Document: NUREG-0800
Document ID: 3320f197-9b8e-4c8c-a548-d533a1f691f4
Document Type: srp
Title: RADIOLOGICAL CONSEQUENCES OF A CONTROL ROD EJECTION ACCIDENT (PWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350416.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.8
CFR Part: 
CFR Title: 

Content:
.e., containment leakage and secondary system leakage outside containment). The actual doses for the postulated accident would be a composite of the doses computed for the independent releases via the containment building and through the secondary system. However, both doses should be presented. The whole-body and thyroid doses calculated by the staff and the applicant are compared with the acceptance criteria stated in subsection II. If the doses for either release path approach the acceptance criteria, cal- culation of representative composite cases should be considered (the AEB branch chief should be consulted). If the doses resulting from the releases through the secondary system exceed the acceptance criteria specified in subsection II above, then a reduction of the technical specification limit on primary-secondary system leakage should be considered. If the doses resulting from the potential releases from the primary containment exceed the specified limits, then a reduction of the pressure setpoint for actuation of the containment sprays may be considered to obtain credit for spray removal of the fission products. IV. EVALUATION FINDINGS The reviewer verifies that sufficient information has been provided by the applicant and that the applicant's analysis and.the staff's independent calcu- lations support conclusions such as the following, to be included with the AEB input to the staff's safety evaluation report: The staff has reviewed the applicant's analysis of the control rod ejection accident and has performed an independent calculation of the radiological consequences following the accident. The staff concludes that the distances to the exclusion area and to the low population zone boundaries for the (insert PLANT NAME) site, in conjunction with the operation of the dose mitigating ESF systems, are sufficient to provide reasonable assurance that the calculated 15.4.8-7 Rev. 1 - July 1981 radiological consequences are well within the exposure guidelines as