Document: NUREG-0800
Document ID: 96afb1d6-6ce9-41e4-b4ec-1fc7747bc0b2
Document Type: srp
Title: Revision 8 – January 2021
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML2033/ML20339A647.pdf
Revision Date: 2023-05
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
One of the systems shall use control rods, preferably including a positive means for inserting the rods, and shall be capable of reliably controlling reactivity changes to assure that under conditions of normal operation, including anticipated operational occurrences, and with appropriate margin for malfunctions such as stuck rods, specified acceptable fuel design limits are not exceeded. The second reactivity control system shall be capable of reliably controlling the rate of reactivity changes resulting from planned, normal power changes (including xenon burnout) to assure acceptable fuel design limits are not exceeded. One of the systems shall be capable of holding the reactor core subcritical under cold conditions. • The regulations in 10 CFR Part 52, “Licenses, certifications, and approvals for nuclear power plants,” govern applications for early site permits, DCs, COLs, SDAs, and manufacturing licenses (MLs) for nuclear power facilities. • The regulations in 10 CFR Part 100, “Reactor site criteria,” Subpart A, “Evaluation Factors for Stationary Power Reactor Site Applications Before January 10, 1997 and for BTP 7-19-6 Revision 8 – January 2021 Testing Reactors,” apply to holders of and applicants for OLs whose CPs were issued before January 10, 1997, and required the CP applicant to assume a fission product release from the core for use in deriving an exclusion area, a low-population zone, and population center distance. The dose criteria in 10 CFR 100.11(a) are commonly referred to as “site dose guideline values” and provide reference values for site evaluation, which can also be used as acceptance criteria for evaluating the adequacy of DI&C design by considering the consequences of a CCF concurrent with a design-basis event (DBE). • In 10 CFR 50.67, “Accident source term,” the NRC provides dose guideline values for analysis of the acceptability of a fission product release from a currently operating NPP as an alternative source