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:
ontamination of the facility. 10.4.8, STEAM GENERATOR BLOWDOWN SYSTEM - as it relates to limiting and reducing radioactive fission, activation and corrosion products within the system piping tanks and vessels, including the associated filtration and purification media, providing design features to limit ORE during operation, testing and maintenance, and providing design features to minimize contamination of the facility. . 11, RADIOACTIVE WASTE MANAGEMENT, as it relates to the description of the design features provided for containment, shielding and handling material contained within the radioactive waste management system, provisions for maintaining ORE ALARA during routine operation, AOO and DBEs, and providing design features to minimize contamination of the facility. 14, RADIATION PROTECTION – INSPECTIONS, TESTS, ANALYSES, AND ACCEPTANCE CRITERIA – as it relates to ITAAC for radiation protection equipment and equipment provided to reduce ORE. 16.0, TECHNICAL SPECIFICATIONS (TSs) – as it relates to proposed alternate controls for High Radiation Areas and Very High Radiation Areas, and any requirements for radiation monitors described in Chapter 12. II. ACCEPTANCE CRITERIA Requirements Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 1. 10 CFR 20.1101(b) and the definition of ALARA in 10 CFR 20.1003, as they relate to persons involved in licensed activities making every reasonable effort, including engineering controls to maintain radiation exposures ALARA. 2. 10 CFR 20.1201, as it relates to occupational dose limits for adults. 3. 10 CFR 20.1201, 10 CFR 20.1202, 10 CFR 20.1203, 10 CFR 20.1204, 10 CFR 20.1701, and 10 CFR 20.1702, as they relate to design features, ventilation, monitoring, and dose assessment for controlling the intake of radioactive materials. 4. 10 CFR 20.1301 and 10 CFR 20.1302, as they relate to the facility design features that impact the radiation exposure to a member of the