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:
e 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 requirements of 10 CFR Part 100 for all release paths following a LOCA is discussed in SRP Section 15.6.5, Appendix A, and the staff's recommen- dations are contained in the "Evaluation Findings" of that SRP section. 15.6.5-25 Rev. 1 - July 1981 V. IMPLEMENTATION. The following provides guidance to applicants and licensees regarding the staff's plans for using this SRP section. Except in those cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described herein will be used by the staff in its evaluation of con- formance with Commission regulations. Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guides. V. REFERENCES 1. Regulatory Guide 1.96, "Design of Main Steam Isolation Valve Leakage Control Systems for Boiling Water Reactor Nuclear Power Plants." 2. 10 CFR Part 100, Paragraph 11, "Determination of Exclusion Area, Low Population Zone, and Population Center Distance." 3. Regulatory Guide 1.3, "Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss-of-Coolant Accident for Boiling Water Reactors." Revision 2.. 4. Computer codes are currently under development. Documentation will be published in a NUREG report. 15.6.5-26 Rev. 1 - July 1981