Document: NUREG-0800
Document ID: 55e187c7-8e17-41ed-a88e-0205d1317fb6
Document Type: srp
Title: - 12.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1315/ML13151A475.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.3
CFR Part: 
CFR Title: 

Content:
conditions, including the criteria for placement, called for in Section 12.3.4 of RG 1.70 (CP PSAR and updates in the OL FSAR) or Section C.I.12.3.4 of RG 1.206 (DC FSAR or COL FSAR to the extent that they are not addressed in a referenced certified design). B. The criteria and method for obtaining representative in-plant airborne radioactivity concentrations in work areas (CP PSAR and updates in the OL 12.3-12.4-5 Revision 5 – September 2013 FSAR, DC FSAR, or the COL FSAR to the extent that they are not addressed in a referenced certified design). C. Description of procedures for locating suspected high-activity areas. D. Information describing the implementation of radiation monitoring equipment criteria listed in RGs 8.2, 8.8, 8.25, RG 1.97, branch technical position (BTP) 7-10 and American National Standards Institute/Health Physics Society (ANSI/HPS) Standard N13.1-1999, and information describing any proposed alternatives (CP PSAR and updates in the OL FSAR, DC FSAR, or the COL FSAR to the extent that they are not addressed in a referenced certified design). E. Description of the in-containment high-range radiation monitoring capability after an accident, in accordance with 10 CFR 50.34(f)(2)(xvii), Item II.F.1.3 of NUREG-0737, RG 1.97, BTP 7-10 and 10 CFR Part 50, Appendix E VI.2(a). F. Description of in plant radiation airborne radioactivity monitoring system in accordance with 10 CFR 50.34(f)(2)(xxvii), Item III.D.3.3 of NUREG-0737, RG 1.97 and BTP 7-10. G. Description of locations for fixed radiation monitors in accordance with ANSI/American Nuclear Society (ANS)/Health Physics Society Standards Committee (HPSSC) Standard ANSI/ANS/HPSSC-6.8.1 H. Description of radiation monitors in areas where special nuclear material is handled or stored in accordance with 10 CFR 50.68 or 10 CFR 70.24. 5. Dose Assessment A. The description of the basis for the dose assessment process, providing detailed information as to expected occupancy of plant radiation areas for