Document: NUREG-0800
Document ID: 145ec0f9-012b-4669-9627-ed1b1d0cce95
Document Type: srp
Title: THERMAL AND HYDRAULIC DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070412.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.4
CFR Part: 
CFR Title: 

Content:
s Branch (HICB) will review the core protection and reactor protection hardware for compliance with requirements applicable to reactor trip systems as part of its primary review responsibility for SRP Section 7.2. HICB will 17 also review the Inadequate Core Cooling (ICC) monitoring system hardware for compliance with requirements applicable to information systems important to safety as part of its primary review responsibility for SRP Section 7.5.18 3. The Human Factors Assessment Branch (HHFB) will review the applicant’s training for use of the loose parts monitor in accordance with its review responsibility for SRP Section 13.2.1. HHFB will also review emergency procedure guidelines (EPGs) and 19 associated programs for development of plant-specific emergency operating procedures (EOPs), including those for recognition of and response to inadequate core cooling conditions, as part of its primary review responsibility for SRP Section 13.5.2. The HHFB will also review human factors aspects of information displays as part of its 20 primary review responsibility for SRP Section 18.21 4. For new plant applicants, the Probabilistic Safety Assessment Branch (SPSB) coordinates and performs shutdown risk assessment reviews as part of its primary review responsibility for SRP Section 19.1 (Proposed). 22 For those areas of review identified above as being reviewed as part of the review responsibility of other branches, the acceptance criteria and their methods of application are contained in the referenced SRP sections. The results of these reviews will be used by SRXB to complete the overall evaluation of the thermal-hydraulic review and will be incorporated into the Safety Evaluation Report (SER).23 DRAFT Rev. 2 - April 1996 4.4-4 II. ACCEPTANCE CRITERIA The thermal and hydraulic design of the reactor core and the RCS, as described in the applicant's safety analysis report (SAR), is acceptable if the design is in accordance with the following criteria:24 A. The CPB