Document: NUREG-0800
Document ID: 3006d57d-d68e-41da-8ef9-9217d041a456
Document Type: srp
Title: RADIOLOGICAL CONSEQUENCES OF A DESIGN BASIS LOSS-OF-COOLANT
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350166.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.5
CFR Part: 
CFR Title: 

Content:
case-by-case basis. IV. EVALUATION FINDINGS The reviewer verifies that the applicant has provided sufficient information for an independent staff calculation of the thyroid and whole-body doses due to MSIV leakage and operation of the MSIVLCS as a fission product release path following a postulated LOCA. The doses are reported in the safety evaluation report (SER) in Table 15. under SER Section 15. , "LOCA Radiological Consequences," in accordance with SRP Section 15.673, Appendix A. The same SER section also includes the staff's findings with respect to the total calculated doses from all release paths and with respect to the acceptability of the exclusion area and.low population zone boundaries on the basis of the total calculated doses in accordance with the guideline values of 10 CFR Part 100. Following the summary section on the total radiological consequences, separate subsections present the staff's evaluation and findings for each specific fis- sion product release path. For the MSIV leakage and operation of the MSIVLCS reviewed under SRP Section 15.6.5, Appendix D, the staff's review and independent calculations should support a conclusion of the following type: The staff has reviewed the applicant's analysis and has independently evaluated the radiation doses resulting from main steam isolation valve leakage and operation of the main steam isolation valve leakage control system following a postulated LOCA assuming a single failure that is most adverse from the standpoint of radiological consequences. The analysis included the influence of fission product removal systems, delay times, and various release paths. The results of this calcula- tion are reported in Table 15- . The review has established that the applicant's design is effectTve in limiting the radiological con- sequences due to the main steam isolation valve leakage or due to operation of the MSIVLCS. The acceptability of the exclusion-area and the low population boundaries in meeting the