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:
quences associated with the operation of the MSIVLCS following a postulated LOCA are combined, under SRP Section 15.6.5, Appendix A, Rev. 1 - July 1981 USNRC STANDARD REVIEW PLAN Standard review plans are prepared for the guidance of the Office of Nuclear Reactor Regulation staff responsible for the review of applications to construct and operate nuclear power plants. These documents are made available to the public as part of the Commission's policy to inform the nuclear Industry and the general public of regulatory procedures and policies. Standard review plans are not substitutes for regulatory guides or the Commission's regulations and compliance with them Is not required. The standard review plan sections are keyed to the Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants. Not all sections of the Standard Format have a corresponding review plan. Published standard review plans will be revised periodically, as appropriate. to accommodate comments and to reflect new informa- tion and experience. Comments and suggestions for Improvement will be considered and should be sent to the U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Washington, D.C. 2055 with the consequences from other LOCA fission product release paths to determine the total calculated radiological consequences from the hypothetical LOCA. The acceptability of the site, with' respect to the total radiological consequences, is determined by the adequacy of the exclusion area and low population zone boundary distances in conjunction 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, paragraph 11 (Ref. 2), and for a construction permit application, the total doses should be within the guideline values of Regulatory Guide 1.3 (Ref. 3). The acceptability is determined under SRP Section 15.6.5, Appendix A. III. REVIEW PROCEDURES The reviewer