Document: NUREG-0800
Document ID: c857bf88-7f70-4d0a-a004-bb765dcfa21b
Document Type: srp
Title: RADIATION SOURCES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070710496.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.2
CFR Part: 
CFR Title: 

Content:
REVIEW RESPONSIBILITIES Primary - Organization responsible for the review of health physics issues. Secondary - None I. AREAS OF REVIEW The staff will review the applicant’s preliminary safety analysis report (PSAR) for a construction permit (CP) or final safety analysis report (FSAR) for an operating license (OL), design certification (DC), or combined license (COL) as it relates to radiation sources in normal operations, anticipated operational occurrences, and accident conditions affecting inplant radiation protection. The specific areas of review are as follows: 1. Contained Sources. The description of radiation sources, during normal operations and accident conditions in the plant, is used as the basis for designing the radiation protection program and for shield design calculations. (SAR Chapter 11 describes the sources contained in equipment of the radioactive waste management systems.) This description should include isotopic composition, location in the plant, source strength and source geometry, and the basis for the values (in the CP PSAR and updated in the OL FSAR, DC FSAR, or COL FSAR or, for sources not described in a referenced certified design, the COL FSAR). The descriptions should include any required radiation sources containing byproduct, source, and special nuclear materials. 12.2-2 Revision 3 - March 2007 2. Airborne Radioactive Material Sources. The staff will review the description of airborne radioactive material sources in the plant considered in the design of the ventilation systems and used for the design of personnel protective measures and for dose assessment. (SAR Chapter 11 contains the description for airborne sources to be considered for their contribution to the plant effluent releases, through equipment of the radioactive waste management systems or the plant ventilation system.) This description should include a tabulation of the calculated concentrations of radioactive material, by nuclide, expected during normal operation,