Document: NUREG-0800
Document ID: c4b10c9f-d82d-4bdd-884b-b83cba562a74
Document Type: srp
Title: Appendix A
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350158.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.5
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CFR Title: 

Content:
reasonable assurance that the 10 CFR Part 100 guideline values can be met at the operating license (OL) review stage. 2. The model for and the calculation of the post-LOCA leakage contribution -to the total whole body and thyroid doses of a hypothetical LOCA are acceptable if they incorporate the appropriate conservative design basis assumptions outlined in the regulatory positions of Regulatory Guide 1.3 (Ref. 2) for a BWk facility and of Regulatory Guide 1.4 (Ref. 3) for a 15.6.5-10 Rev. 1 - July 1981 PWR facility with the exception of the guidelines for the atmospheric dispersion fusion factors (X/Q values). The acceptability of the X/Q values is determined under SRP Section 2.3.4. III. REVIEW PROCEbURES The reviewer selects and emphasizes aspects of the areas covered by this appendix as may be appropriate for a particular case. The decision as to which areas need to be given attention and emphasis in the review is based on a determination of whether the material presented is similar to that recently reviewed on other plants and whether items of special safety significance are involved. Review steps (1) through (8) below apply to the containment leakage contribution and step (9) applies to the total radiological consequences. 1. The design (stretch) power level of the core is taken from the applicant's safety analysis report (SAR). The core is assumed to have operated at this power level for a sufficiently extended period (typically about 3 years) such that the maximum equilibrium fission product inventory is present. At the time of the accident, 25% of all the equilibrium iodine fission products and 100% of the noble gas fission products are assumed available for release from the containment within a very short time (effec- tively instantaneously) after the accident. The iodine is assumed to be composed of 91% elemental iodine, 4% organic iodides, and 5% particulate iodine. 2. The reviewer ascertains the type of containment system used based on information in