Document: NUREG-0800
Document ID: 8da52d2b-9980-4076-8056-2cafebb25ed6
Document Type: srp
Title: THERMAL AND HYDRAULIC DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550060.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.4
CFR Part: 
CFR Title: 

Content:
ing techniques that rely on in- core or ex-core neutron sensor inputs are evaluated. 2. The review of anticipated transients without scram (ATWS) and coupled neutronic- thermal-hydraulic instabilities for BWRs is performed under SRP Sections 15.8 and 15.9, respectively. 3. The review of the adequacy of components and structures under accident loads and the preoperational vibration test program is performed under SRP Sections 3.9.3 and 3.9.6. 4. The review of the core protection and reactor protection hardware to determine compliance with the requirements applicable to reactor trip systems is performed under SRP Section 7.2. 5. The review of ICC monitoring system hardware to determine compliance with the requirements applicable to information systems important to safety is performed under SRP Section 7.5. 6. The review of the applicant’s training program is performed under SRP Sections 13.2.1 and 13.2.2. 7. The review of emergency procedure guidelines (EPGs) and associated programs for development of plant-specific emergency operating procedures, including those associated with recognizing and responding to inadequate core cooling (ICC) conditions, is performed under SRP Section 13.3. 8. The review of the human factors aspects of information displays is performed under SRP Chapter 18. 9. For new plant applicants, the review of shutdown risk assessment is performed under SRP Chapter 19. 4.4-4 Revision 2 - March 2007 The primary review organizations will use the results of these reviews to complete the overall evaluation of the thermal-hydraulic review; the results will also be incorporated into the safety evaluation report (SER). 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) 10, as it relates to whether the design of the reactor core