Document: NUREG-0800
Document ID: 36318a40-8941-4ccf-8898-197c33065a4b
Document Type: srp
Title: OPERATIONAL RADIATION PROTECTION PROGRAM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1007/ML100740544.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.5
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ods of compliance with the NRC regulations. The following RGs, NUREGs, and industry standards provide information, recommendations, and guidance and in general describe a basis acceptable to the staff to implement the requirements of 10 CFR Part 19, 10 CFR Part 20, and 10 CFR Part 50: 1. RG 1.8, as it relates to compliance with the Commission’s regulations regarding qualification of nuclear power plant personnel 1For Part 50 applicants not listed in 10 CFR 50.34(f), the provisions of 50.34(f) will be made a requirement during the licensing process. 2. RG 1.33, as it relates to compliance with the Commission’s quality assurance regulatory requirements during nuclear power plant operations. 3. Revision 3 of RG 1.97, as it relates to compliance with the Commission’s regulations to provide instrumentation to monitor plant variables and systems during and following an accident. 4. RG 8.2, as it relates to general information on radiation monitoring programs for administrative personnel. 12.5-7 Revision 4 - May 2010 5. RG 8.4, as it relates to standards for direct-reading and indirect-reading pocket dosimeters used for personnel dose or dose rate measurements. 6. RG 8.6, as it relates to testing the operating characteristics of Geiger-Mueller counters before making calibrations and measurements. 7. RG 8.7, as it relates to the specification of records necessary to describe the ORE of individuals and to the conditions under which the exposure may occur. 8. RG 8.8, as it relates to meeting the requirements of 10 CFR 20.1101(b) and the definition of ALARA in 10 CFR 20.1003 by providing radiation protection information pertaining to actions taken during the design, construction, operation, and decommissioning to ensure that ORE remains ALARA. 9. RG 8.9, as it relates to appropriate concepts, models, equations, and assumptions to be used in determining the extent of an individual’s intake of radioactive materials and resulting committed organ dose. 10. RG 8.10, as it