Document: NUREG-0800
Document ID: 968e9bbe-e8ca-4639-a8d2-f96483377bae
Document Type: srp
Title: - 12.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1219/ML12191A219.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.3
CFR Part: 
CFR Title: 

Content:
uired fluid leakage detection criteria. G. To the extent that it is not covered in BTP 5-1 or application Section 11.5, the specified sensitivity of radiation monitoring equipment provided for Primary to Secondary Leakage detection (i.e. requirements specified in the EPRI guidance forming the basis for NEI 97-06) is acceptable if it is capable of meeting the required fluid leakage detection criteria. H. To the extent that it is not covered in application Sections 7.5 and 11.5, the description of the Emergency Response Data System is acceptable if the radiation monitoring system components required by 10 CFR Part 50. Appendix E VI.2(a) is provided. 12.3-12.4-22 Draft Revision 5 – October 2012 5. Dose Assessment The dose assessment will be acceptable if it documents the assumptions made, calculations used, results for each radiation zone (including numbers and types of workers involved in each), expected and design dose rates, and projected annual person-Sievert (person-rem) doses, in accordance with RG 8.19. If applicable, the applicant’s dose assessment of construction workers on a facility adjacent to an existing nuclear unit(s), will be acceptable if it documents the assumptions made, calculations used, results for the areas where construction workers will be located (including numbers of construction workers), expected dose contributions (from direct, gaseous, and liquid sources), and projected person-Sievert (person-rem) doses, consistent with RG 1.206 Subsection C.I.12.3.5. 6. Minimization of Contamination Compliance with 10 CFR 20.1406 requires the applicant to describe how facility design and procedures for operation will minimize, to the extent practicable, contamination of the facility and the environment, facilitate eventual decommissioning, and minimize, to the extent practicable, the generation of radioactive waste. The acceptability of these features will be based on the guidance contained in RG 4.21 and Appendix 12.3-12.4-A (CP PSAR and updates in