Document: NUREG-0800
Document ID: 164d26ee-2125-481e-9fae-fb7b05365716
Document Type: srp
Title: RESIDUAL HEAT REMOVAL (RHR) SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340635.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.4.7
CFR Part: 
CFR Title: 

Content:
ions 7.1 and 7.4 reviews the instrumentation and control systems for the RHR system to determine that it will perform its design function as required and conform to all applicable acceptance criteria. The ICSB also reviews the provisions taken to meet GDC 19 with respect to equipment outside of the control room for hot and cold shutdown. The Radiological Assessment Branch (RAB) has primary review responsibility for SRP Section 12.1 through 12.5 including Task Action Plan items II.B.2 of NUREG-0737 and NUREG-0718 which involve a radiation and shielding design review and corrective actions taken to ensure adequate access to vital areas and protection of safety equipment (CPs and OLs). The review for Fire Protection, Technical Specifications, and Quality Asurance are coordinated and performed by the CMEB, Standardization and Special Projects Branch (SSPB) and Quality Assurance Branch (QAB) as part of their primary I review responsibility for SRP Sections 9.5.1, 16.0 and 17.0, respectively. For those areas of review identified above as being reviewed as part of the primary review responsibility of other branches, the acceptance criteria necessary for the review and their methods of application are contained in the referenced SRP Section of the corresponding primary branch. II. ACCEPTANCE CRITERIA The Reactor Systems Branch acceptance criteria are based on meeting the requirements of the following regulations: A. General Design Criterion 2 with respect to the seismic design of systems, structures and components whose failure could cause an unacceptable reduc- tion in the capability of the residual heat removal system. Acceptability is based on meeting position C-2 of Regulatory Guide 1.29 or its equivalent. B. General Design Criterion 4, as related to dynamic effects associated with flow instabilities and loads (e.g., water hammer). C. General Design Criterion 5 which requires that any sharing among nuclear power units of structures, systems and components important to