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:
with the organization responsible for the review of electrical systems. (l) 10 CFR 50.34(f)(2)(xxii): Addressing (TMI Action Plan Item II.K.2.9) Failure Modes and Effects Analysis of Integrated Control System “Perform a failure modes and effects analysis of the integrated control system (ICS) to include consideration of failures and effects of input and output signals to the ICS. (Applicable to Babcock and Wilcox (B&W) - designed plants only.)” Applicability - Control systems in B&W-designed plants. Review Methods - The recommendations of the generic failure modes and effects analysis described in BAW-1564, “Integrated Control System Reliability Analysis,” should be incorporated into the design if this analysis applies to the plant. Otherwise a plant-specific failure modes and effects analysis should be conducted in accordance with U.S. Nuclear Regulatory Commission (NRC) orders on B&W plants, and with NUREG-0694. The evaluation of conformance to this requirement should be addressed in the review of Section 7.7 of the SAR. (m) 10 CFR 50.34(f)(2)(xxiii): Addressing (TMI Action Plan Item II.K.2.10) Anticipatory Trip on Loss of Main Feedwater or Turbine Trip. “Provide, as part of the reactor protection system, an anticipatory reactor trip that would be actuated on loss of main feedwater and on turbine trip. (Applicable to B&W-designed plants only).” Applicability - RTS in B&W-designed plants. Review Methods - The design should comply with the guidance of NUREG-0694, Item II.K.1 and either IEEE Std 279-1971 or IEEE Std 603-1991. SRP Appendix 7.1-B, Subsection 4.5 and SRP Appendix 7.1-C, Subsection 5.12 provide guidance on the review of auxiliary features such as anticipatory trips. The evaluation of conformance to this requirement should be addressed in the review 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