Document: NUREG-0800
Document ID: d2f0cc81-920c-4065-b74b-67114ba68b0e
Document Type: srp
Title: through 7.9 of the SAR. Where exceptions are taken to the guidance provided by regulatory guides, and
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0525/ML052500493.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.2
CFR Part: 
CFR Title: 

Content:
s are powered from vital buses, (B) motive and control power connections to the emergency power sources are through devices qualified in accordance with requirements applicable to systems important to safety, and (C) electric power is provided from emergency power sources. (Applicable to PWRs only)." Applicability — Information systems important to safety in PWRs, and safe shutdown systems. Review Methods — Pressurizer level indication, block valve position indication, and relief valve position indication should be supplied from a source of emergency power in the event of a loss of offsite power. The power supplies should conform with the guidance of NUREG-0737. The evaluation of conformance with this Rev. 4 — June 1997 SRP 7.1-A-6 requirement should be addressed in the review of Sections 7.4 and 7.5 of the SAR. The review of this requirement should be coordinated with the Electrical Engineering Branch (EELB). j. 50.34(f)(2)(xxii) [TMI Action Plan Item II.K.2.9] Failure Mode and Effect 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 B&W-designed plants only)." Applicability — Control systems in Babcock and Wilcox (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 mode and effect analysis should be conducted in accordance with NRC orders on B&W plants, and NUREG-0694. The evaluation of conformance with this requirement should be addressed in the review of Section 7.7 of the SAR. k. 50.34(f)(2)(xxiii) [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