Document: NUREG-0800
Document ID: 49aefb86-1adb-4b3c-826f-480e32947595
Document Type: srp
Title: Radiological Consequence Analyses Using Alternative Source Terms
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0037/ML003734190.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.0.1
CFR Part: 
CFR Title: 

Content:
sm to implement a modification involving a reanalysis of the radiological consequences of a DBA LOCA. However, this licensee could extend use of the timing characteristic to adjust the closure time on isolation valves not included in the initial approved implementation in accordance with 10 CFR 50.59. The review associated with an application for the use of an AST is largely dependent on the scope and nature of the associated plant modifications being proposed. Thus, the areas of review identified in other SRP sections may be applicable and should be considered in performing the review. This SRP section covers the review by SPSB of the radiological consequences of DBAs. The review includes the following: 1. Reviews of the AST implementation to ensure that all significant radiological and nonradiological impacts have been considered. Radiological consequences that should be considered include the following: a. Exclusion area boundary (EAB), low population zone (LPZ), and control room habitability (10 CFR 50.67) b. Emergency response center habitability (paragraph IV.E.8 of Appendix E to 10 CFR Part 50) c. Equipment environmental qualification (10 CFR 50.49) 1 Facility-specific licensing commitments may affect applicability of NUREG-0737 (Ref. 2) items. 15.0.1-4 Rev. 0 -- July 2000 d. Environmental assessments (10 CFR Part 51) e. Post-accident access shielding (NUREG-0737, II.B.2)1 f. Post-accident sampling capability (NUREG-0737, II.B.3) g. Post-accident monitoring (NUREG-0737, II.F.1) h. Leakage control (NUREG-0737, III.D.1.1) i. Emergency response facilities (NUREG-0737, III.A.1.2) j. Control room habitability (NUREG-0737, III.D.3.4) 2. A review of the sequence of accident events as described by the licensee to ensure that the case that maximizes the radioactivity release has been considered. 3. A review of the core inventory determined by the licensee to ensure that it is consistent with the current licensing basis rated thermal power, enrichment, and burnup. 4. A