Document: NUREG-0800
Document ID: 11a2be5f-50e6-47c7-beee-25b5049ab4bb
Document Type: srp
Title: REACTOR TRIP SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350474.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.2
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Content:
REVIEW RESPONSIBILITIES Primary - Instrumentation and.Control Systems Branch (ICSB) Secondary - None I. AREAS OF REVIEW This SRP section describes the review of the reactor trip system (RTS), which is part of the reactor protection system, and includes those power sources, sensors, initiation circuits, logic matrices, bypasses, interlocks, racks, panels and con- trol boards, and actuation and actuated devices, that are required to initiate reactor shutdown. The RTS is designed to initiate automatically the reactivity control system (control rods), to assure that specified acceptable fuel design limits are not exceeded. The review of the controls, inhibits, and interlocks for the withdrawal, insertion, and sequence of control rods is included in Section 7.7 of the safety analysis report (SAR). The objectives of the review are to confirm that the RTS satisfies the requirements of the acceptance criteria and guidelines applicable to the protection system and will perform its safety function during all plant conditions for which they are required. The review performed for a construction permit application may be based on preliminary designs and the depth of information need only be sufficient to pro- vide reasonable assurance that the final design will conform to the design bases and applicable criteria with an adequate margin for safety. The review performed for an operating license (OL) application is based upon detailed design information that confirms that the final design conforms to the design bases and applicable criteria. The depth of the review for an OL application should be sufficient to conclude that the requirements of the Commission regulations have been satisfied. The depth of the review for the balance of the criteria applicable to the pro- tection system should be sufficient to conclude that the systems conform with the guidelines to the extent required to support the findings of conformance to the regulations. Rev. 2 - July 1981 USNRC STANDARD REVIEW