Document: NUREG-0800
Document ID: 0c942a2c-afa6-4bbd-8f3f-4eede9dc146e
Document Type: srp
Title: - 12.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350048.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.3
CFR Part: 
CFR Title: 

Content:
ielding and appropriate containment and filtering systems. 8. 10 CFR Part 70, Section 70.24, "Criticality Accident Requirements" as it relates to procedures and criteria for monitoring for criticality accidents involving special nuclear material. The following regulatory guides, NUREGs and industry standards provide informa- tion, recommendations and guidance and in general describe a basis acceptable to the staff for implementing the requirements of the regulations identified above: 1. Regulatory Guide 1.3, "Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss-of-Coolant Accident for Boiling Waters Reactors," as it relates to assumptions used in evaluating gaseous concentrations of radionuclides in containment and plant systems, following a loss-of-coolant-accident for BWRs. 2. Re ulatory Guide 1.4. "Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss-of-Coolant Accident for Pressurized Water Reactors," as it relates to assumptions used in evaluating gaseous concentrations of radionuclides in containment and plant systems, follow- ing a loss-of-coolant accident for PWRs. 3. Regulatory Guide 1.7, "Control of Combustible Gas Concentrations in Containment Following a Loss-of-Coolant Accident," as it relates to methods ?or determining gaseous concentrations of radionuclides in con- tainment following an accident. 12.3-4 Rev. 2 - July 1981 4. Regulatory Guide 1.52, Design, Testing, and Maintenance Criteria for Post-Accident Enaineered-SafeUy-Feature Atmosphere Cleanup System Air Filtration and Absorption Units of Light-Water Cooled Nuclear Power Plants," as it relates to radiation protection considerations for ESF atmosphere cleanup systems operable under postulated OBA conditions, to be designated as "primary systems." 5. Regulatory Guide 1.69, "Concrete Radiation Shields for Nuclear Power Plants,' as it relates to the requirements and recommended practices con- tained in ANSI N101.6 - 1972, "Concrete Radiation