Document: NUREG-0800
Document ID: 3ea2f0ac-4d7e-464a-b1c4-390c3970f642
Document Type: srp
Title: provides specific thermal-hydraulic criteria.  The available radioactive fission product
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070740002.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.4
CFR Part: 
CFR Title: 

Content:
inventory in fuel rods (i.e., the gap inventory expressed as a release fraction) is provided to those organizations that estimate the radiological consequences of plant releases in accordance with SRP Chapter 15. Fuel stored energy, flow blockage, peak cladding temperature, and equivalent cladding reacted (ECR) limits defined in SRP Section 4.2 are provided to those organizations that review Chapter 15. Other SRP sections interface with this section as follows: 1. Review of the nuclear design of the fuel assemblies, control systems, and reactor core under SRP Section 4.3. 2. Review of the thermal margins, the effects of corrosion products (crud), and the acceptability of hydraulic loads under SRP Section 4.4. 4.2-4 Revision 3 - March 2007 3. Review of the design bases for the emergency core cooling system (ECCS), including GDC and ECCS acceptance criteria, under SRP Section 6.3. 4. Review of the postulated fuel failures resulting from overheating of cladding, overheating of fuel pellets, excessive fuel enthalpy, pellet/cladding interaction (PCI), and bursting under Chapter 15. 5. Review of the control rod drive mechanism design in SRP Section 3.9.4 and the reactor internals design under SRP Section 3.9.5. 6. Review of the estimates of radiological dose consequences under Chapter 15. The specific acceptance criteria and review procedures are contained in the referenced SRP sections. II. ACCEPTANCE CRITERIA Requirements Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 1. 10 CFR 50.46, 10 CFR 50.34, and 10 CFR 50.67, as they relate to the cooling performance analysis of the ECCS using an acceptable evaluation model and establishing acceptance criteria for light-water nuclear power reactor ECCSs. 2. 10 CFR Part 100 and 10 CFR 50.67, as they relate to determining the acceptability of a reactor site based on calculating the exposure to an individual as a result of fission product releases to the environment