Document: NUREG-0800
Document ID: 93972ce6-c834-45c7-95fb-aa2f7ac9c8fd
Document Type: srp
Title: - 15.3.4-3
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550012.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.3.3
CFR Part: 
CFR Title: 

Content:
Revision 3 - March 2007 Review Interfaces Other SRP sections interface with this section as follows: 1. General information on transient and accident analyses is provided in SRP Section 15.0. 2. Design basis radiological consequence analyses associated with design basis accidents are reviewed under SRP Section 15.0.3. 3. Instrumentation and controls aspects of the sequence described in the SAR is reviewed to confirm that reactor and plant protection and safeguards controls and instrumentation systems will function as assumed in the safety analysis under SRP Sections 7.2 through 7.5. 4. Fracture toughness properties of the reactor coolant pressure boundary and reactor vessel are reviewed under Sections 5.2.3 and 5.3.1. 5. Integrity of the reactor coolant pump seals is performed under SRP Section 9.2.2. 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. General Design Criterion (GDC) 17, as it relates to providing onsite and offsite electric power systems to ensure that structures, systems, and components important to safety will function. The safety function for each system (assuming the other system is not functioning) shall be to provide sufficient capacity and capability to ensure that design conditions of the reactor coolant pressure boundary are not exceeded and the core is cooled in the event of postulated accidents. 2. General Design Criteria 27 (GDC 27) and 28 (GDC 28), as they relate to the reactor coolant system being designed with appropriate margin to ensure that the capability to cool the core is maintained. 3. General Design Criterion 31 (GDC 31), as it relates to the reactor coolant system being designed with sufficient margin to ensure that the boundary behaves in a non-brittle manner and that the probability of propagating fracture is minimized. 4. 10 CFR