Document: NUREG-0800
Document ID: 0e5dd9d7-fef0-46ca-ba6d-f3d06f5c7801
Document Type: srp
Title: REACTOR SYSTEMS (Tier 1)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070662.pdf
Revision Date: 2023-06
Chapter: 14
Section ID: 14.3.4
CFR Part: 
CFR Title: 

Content:
ater Reactor Designs." The SRM related to this is dated July 21, 1993. Tier 1 should be reviewed for treatment of design information proportional to the safety significance of the SSC for that system. Many items may be judged to be important to safety, and thus should be included in Tier 1. The following issues are identified to ensure comprehensive and consistent treatment in Tier 1 based on the safety significance of the system being reviewed: (1) System purpose and functions (2) Location of system (3) Key design features of the system (4) Seismic and ASME code classifications (5) System operation in various modes (6) Controls, alarms, and displays (7) Logic 14.3.4-3 DRAFT Rev. 0 - April 1996 (8) Interlocks (9) Class 1E electrical power sources and divisions (10) Equipment to be qualified for harsh environments (11) Interface requirements (12) Numeric performance values (13) Accuracy and quality of figures Additionally, standard ITAAC entries should be utilized to verify selected issues, where appropriate. The reviewer should ensure consistent application and treatment of all of the standard ITAAC entries, since most apply to the treatment of issues for reactor systems. Also, the reviewer should utilize the review checklist for fluid systems in Appendix C to SRP Section 14.3. In general, many of the reactor and core cooling systems are classified as safety-related, and therefore many of the characteristics and features of these systems are judged to have safety significance. This is reflected in a relatively higher level of detail in Tier 1 for these systems than other systems of the standard design. Tier 1 should be reviewed to verify that plant safety analyses, such as for core cooling, transients, overpressure protection, steam generator tube rupture, and anticipated transient without scram (ATWS), are adequately addressed. Applicants should provide tables in DCD Tier 2 Section 14.3 to show how the important input parameters used in the transient and accident