Document: NUREG-0800
Document ID: 240b218f-0879-4774-a145-71a59b902d69
Document Type: srp
Title: RADIOLOGICAL CONSEQUENCES OF A DESIGN BASIS LOSS-OF-COOLANT
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350160.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.5
CFR Part: 
CFR Title: 

Content:
junction with the operation of dose-mitigating ESF systems. For operating license applications, the total doses should be within the exposure guidelines of 10 CFR Part, 100, § 100.11 (Ref. 2) and for a construction permit application, the total doses should be within the guideline value of Regulatory Guides 1.3 (Ref. 3) and 1.4 (Ref. 4), as appropriate. This acceptability is determined under.SRP Section 15.6.5, Appendix A. III. REVIEW PROCEDURES The reviewer selects and emphasizes aspects covered by this appendix as appro- priate for a particular case. The judgment of which areas need to be given 15.6.5-16 Rev. 1 - July 1981 attention and emphasis in the review is based on a determination if the mate- rial presented is similar to that recently reviewed on other plants and whether items of special safety significance are involved. The applicant's recirculation leakage assumptions and calculation are compared with previously licensed plants for accuracy and completeness. It is assumed that 50% of the core iodine inventory, based upon the maximum reactor power level, is mixed in the sump water being circulated through the external pip- ing systems (Ref. 1). Credit may be allowed for.radioactive decay of the iodine during the time period from the occurrence of the LOCA up to the begin- ning of recirculation when the sump water is circulated outside the containment. The leakage for calculating the radiological consequences should be the maxi- mum operational leakage and should be taken as two times the sum of the simultaneous leakage from all components in the recirculation systems above which the technical specifications would require declaring such systems to be out of service. The leakage is assumed to occur throughout the accident, starting at the earliest time that the recirculation mode is initiated. For a plant that does not provide an ESF atmosphere filtration system, the dose assessment should also include the leakage from a gross failure of a pas- sive