Document: NUREG-0800
Document ID: d1231348-49d9-4197-8557-69cb2e1eb62a
Document Type: srp
Title: RADIATION SOURCES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1218/ML12186A009.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.2
CFR Part: 
CFR Title: 

Content:
purification media, as determined from the bases, models and assumptions described in Chapter 11. 10.4.8 STEAM GENERATOR BLOWDOWN SYSTEM - as it relates to the types, quantities and concentrations of radioactive fission, activation and corrosion products within the system piping tanks and vessels, filtration media and purification media, as determined from the bases, models and assumptions described in Chapter 11. 11 RADIOACTIVE WASTE MANAGEMENT - as it relates to the description of the methods, models and assumptions used as the bases for determining concentrations and quantities of radioactive in SSCs described in section 12.2, also, as it relates to the description of sources contained in equipment of the radioactive waste management system. 16.0 TECHNICAL SPECIFICATIONS (TSs) - as it relates to the types, quantities and concentrations of radioactive fission, activation and corrosion products within the system piping tanks and vessels, filtration media and purification media, that may be derived from allowable primary-to-secondary leakage or secondary cooling system specific activity. II. ACCEPTANCE CRITERIA Requirements Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 1. 10 CFR 20.1101, 10 CFR 20.1201, 10 CFR 20.1202, and 10 CFR 20.1206, as they relate to limiting occupational radiation doses. 2. 10 CFR 20.1203 and 10 CFR 20.1204, as they relate to limiting average concentrations of airborne radioactive materials to protect individuals and control the intake (inhalation or absorption) of such materials. 3. 10 CFR 20.1207, as it relates to limiting exposure to minors to one-tenth of limits for adults. 12.2-6 Draft Revision 4 – October 2012 4. 10 CFR 20.1301 and 40 CFR Part 190, as it relates to the determination of radiation levels and radioactive materials concentrations within the SSCs and components of the plant, that could affect direct radiation exposure to members of the public. . 5. 10 CFR