Document: NUREG-0800
Document ID: a4cb1b75-ec12-4a5f-9042-da6e8c17fe83
Document Type: srp
Title: and 7.7 of the safety analysis report (SAR).
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0525/ML052500502.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.6
CFR Part: 
CFR Title: 

Content:
ral Design Criterion 2, "Design Basis for Protection Against Natural Phenomena." General Design Criterion 4, "Environmental and Missile Design Basis." General Design Criterion 13, "Instrumentation and Control." General Design Criterion 19, "Control Room." General Design Criterion 20, "Protection Systems Functions." General Design Criterion 21, "Protection System Reliability and Testability." General Design Criterion 22, "Protective System Independence." General Design Criterion 23, "Protection System Failure Modes." General Design Criterion 24, "Separation of Protection and Control Systems." Rev. 4 — June 1997 SRP 7.2-3 General Design Criterion 25, "Protection System Requirements for Reactivity Control Malfunctions." General Design Criterion 29, "Protection Against Anticipated Operational Occurrences." Item II.Q., Defense Against Common-Mode Failures in Digital Instrument and Control Systems, of the Staff Requirements Memorandum on SECY-93-087, "Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light Water Reactor (ALWR) Designs." 2. Additional acceptance criteria applicable to RTS proposed for design certification under 10 CFR 52 10 CFR 52.47(a)(1)(iv), "Resolution of Unresolved and Generic Safety Issues." 10 CFR 52.47(a)(1)(vi), "ITAAC in Design Certification Applications." 10 CFR 52.47(a)(1)(vii), "Interface Requirements." 10 CFR 52.47(a)(2), "Level of Detail." 10 CFR 52.47(b)(2)(i), "Innovative Means of Accomplishing Safety Functions." 3. Additional acceptance criteria applicable to RTS proposed as part of combined license applications under 10 CFR 52 10 CFR 52.79(c), "ITAAC in combined Operating License Applications." As described in Reg. Guide 1.153, "Criteria for Power, Instrumentation and Control Portions of Safety Systems," compliance with IEEE Std 603, "IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations," as modified and supplemented by the regulatory guide, is considered by the NRC staff to