Document: NUREG-0800
Document ID: fabdf65c-d299-4b3a-a971-ae5b21a97177
Document Type: srp
Title: RADIATION SOURCES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1315/ML13151A413.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.2
CFR Part: 
CFR Title: 

Content:
ed until after the rest of this portion of the application has been reviewed against acceptance criteria contained in this SRP section. Furthermore, the staff reviews the ITAAC to ensure that all SSCs in this area of review are identified and addressed as appropriate in accordance with SRP Section 14.3. 4. COL Action Items and Certification Requirements and Restrictions. For a DC application, the review will also address COL action items and requirements and restrictions (e.g., interface requirements and site parameters). 12.2-3 Revision 4 – September 2013 For a COL application referencing a DC, a COL applicant must address COL action items (referred to as COL license information in certain DCs) included in the referenced DC. Additionally, a COL applicant must address requirements and restrictions (e.g., interface requirements and site parameters) included in the referenced DC. Review Interfaces Systems described in the applicant’s submittal may differ from those outlined in the SRP. The staff should use the following recommended section interfaces as the basis for reviewing other supplemental or complementary information provided in the applicant’s submittal for a specific plant design to identify and quantify sources of radioactivity that may require radiation protection design features to minimize ORE and protect equipment: 3.11 ENVIRONMENTAL QUALIFICATION OF MECHANICAL AND ELECTRICAL EQUIPMENT - as it relates to sources of radiation that are used to establish the design basis for the radiation dose to equipment. 4.2 FUEL SYSTEM DESIGN - as it relates to the bases for determining the radioactive content of: irradiated fuel, including fuel burn up, fuel enrichment, fuel bundle materials; irradiated control rods materials; and fuel power density as it relates to the potential amount of radioactive material created by the activation of material deposited in high neutron flux areas, which is available for release into the Reactor Coolant System (RCS) fluid.