Document: NUREG-0800
Document ID: 6813459c-4e76-4630-8395-e948ff46c2b3
Document Type: srp
Title: and 7.5 of the SAR.  The review of this requirement should be coordinated
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1515/ML15159A207.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.4
CFR Part: 
CFR Title: 

Content:
iew of Section 7.2 of the SAR. (n) 10 CFR 50.34(f)(2)(xxiv): Addressing (TMI Action Plan Item II.K.3.23) Central Reactor Vessel Water Level Recording “Provide the capability to record reactor vessel water level in one location on recorders that meet normal accident monitoring recording requirements. (Applicable to BWRs only).” Applicability - Information systems important to safety in BWRs. Review Methods - The capability should be provided to record the water level over the range from the top of the vessel dome to the lowest pressure tap. This range of water level indication should be available in one location on recorders Appendix 7.1-A-10 Draft Revision 6 – August 2015 that meet normal accident monitoring recording requirements. The evaluation of conformance to this requirement should be addressed in the review of Section 7.5 of the SAR. (o) 10 CFR 50.62: Requirements for Reduction of Risk from Anticipated Transients Without Scram (ATWS) Events for Light-Water-Cooled Nuclear Power Plants. 10 CFR 50.62(c)(1) “Each pressurized water reactor must have equipment from sensor output to final actuation device, that is diverse from the reactor trip system, to automatically initiate the auxiliary (or emergency) feedwater system and initiate a turbine trip under conditions indicative of an ATWS. This equipment must be designed to perform its function in a reliable manner and be independent (from sensor output to the final actuation device) from the existing reactor trip system. (2) Each pressurized water reactor manufactured by Combustion Engineering or by Babcock and Wilcox must have a diverse scram system from the sensor output to interruption of power to the control rods. This scram system must be designed to perform its function in a reliable manner and be independent from the existing reactor trip system (from sensor output to interruption of power to the control rods). (3) Each boiling water reactor must have an alternate rod injection (ARI) system that is