Document: NUREG-0800
Document ID: 54e3d49d-900d-4fe8-9297-2fc04501e4e0
Document Type: srp
Title: THERMAL AND HYDRAULIC DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340664.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.4
CFR Part: 
CFR Title: 

Content:
hat the applicant is in compliance with the documentation requirements and design requirements described in item II.F.2 of NUREG-0737 (Ref. 18). The reviewer consults with ICSB and HFEB concerning the design acceptability of the instrumentation and displays and with the Reactor Systems Branch (RSB) and PTRB concerning the acceptability of guidelines and procedures for recognition and response to inadequate core cooling conditions. The applicant's proposed preoperational and initial startup test programs are reviewed to determine that they are consistent with the intent of Regulatory Guide 1.68 (Ref. 15). At the OL stage, the reviewer is to assure that suf- ficient information is provided by the applicant to identify clearly the test objectives, methods of testing, and acceptance criteria. (See par. C.2.b of Reference 15.) The test scope should include verification of any safety analysis codes or methods which could affect the thermal-hydraulic evaluations and which have not been previously verified. The initial startup test should also include a description of plans for a signature analysis to determine alarm setting for the loose parts monitoring system, and a description of test programs for evaluation, qualification and calibration of ICC instrumentation. The reviewer evaluates the proposed test programs to determine if they provide reasonable assurance that the core and reactor coolant system will satisfy functional requirements. As an alternative to this detailed evaluation, the reviewer may compare the core and reactor coolant system design to that of previously reviewed plants. If the design is essentially identical and if the proposed test programs are essentially the same as performed previously on 4.4-6 Rev. 1 - July 1981 other plants, the reviewer may conclude that the proposed test programs are adequate for the core and reactor coolant system. . If the core or the reactor coolant system differs significantly from that of previously reviewed designs, the