Document: NUREG-0800
Document ID: 4865fc6d-b85f-4173-9bca-162fa9fe67d2
Document Type: srp
Title: Appendix 7-A
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0525/ML052500555.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
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Content:
Generating Station Safety Systems." IEEE Std 603-1991. "IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations." NUREG-0493. "A Defense-in-Depth & Diversity Assessment of the RESAR-414 Integrated Protection System." March 1979. NUREG/CR-6303. "Method for Performing Diversity and Defense-in-Depth Analyses of Reactor Protection Systems." December 1994. Regulatory Guide 1.153. "Criteria for Power, Instrumentation, and Control Portions of Safety Systems." Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1996. Regulatory Guide 1.53. "Application of the Single-Failure Criterion to Nuclear Power Plant Protection Systems." Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1973. SECY 91-292. "Digital Computer Systems for Advanced Light-Water Reactors." September 1991. Rev. 4 — June 1997 Appendix 7-A BTP HICB-19-8 SECY-93-087. "Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light-Water Reactor (ALWR) Designs." April 2, 1993. Staff Requirements Memorandum on SECY-93-087. "Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light-Water Reactor (ALWR) Designs." July 15, 1993.