Document: NUREG-0800
Document ID: b41776b4-3baa-48e2-8183-522a8ba8b076
Document Type: srp
Title: OPERATIONAL RADIATION PROTECTION PROGRAM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1218/ML12186A007.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.5
CFR Part: 
CFR Title: 

Content:
ceed exposure limits, to administer and control conditions of radiation work permits, to post radiation areas, to establish radiation access control zones, to control all radioactive material entering or leaving the plant site, and to train plant and visitor personnel in radiation protection policies and procedures and meet the quality assurance guidance of RG 1.33 with respect to the requirements of 10 CFR 20.1101, Appendix B to 10 CFR Part 50, and 10 CFR 71.101. Storage and control of licensed materials in unrestricted areas will be maintained in accordance with 10 CFR 20.1601, 10 CFR 20.1602, 10 CFR 20.1801, 10 CFR 20.1802, 10 CFR 20.1901, and 10 CFR 20.1902. The applicant’s program complies with 10 CFR Part 30, “Rules of General Applicability to Domestic Licensing of Byproduct Material,” 10 CFR Part 40, “Domestic Licensing of Source Material,” and 10 CFR Part 70, “Domestic Licensing of Special Nuclear Material,” as they relate to the requirements for the receipt, storage and use of byproduct, source, and special nuclear material. Facilities and procedures are adequate to provide reasonable assurance that the plant will be operated in a manner that will minimize, to the extent practicable, contamination of the facility and the environment, in accordance with 10 CFR 20.1406. In accordance with the requirements of 10 CFR 50.65(a), consistent with the guidance provided in RG 1.160, procedures are provided to monitor the performance or condition of SSCs, including those that are relied upon to mitigate accidents or transients or are used in plant EOPs, against licensee- established goals in a manner sufficient to provide reasonable assurance that 12.5-23 Draft Revision 5 – October 2012 SSCs important to safety, including those that are relied upon to mitigate accidents or transients or are used in plant EOPs (i.e. radiation monitors or radiation protection features described in Section 12.3), are capable of fulfilling their intended functions. A