Document: NUREG-0800
Document ID: 98022cb7-93d2-45d0-952a-2e2bc1225400
Document Type: srp
Title: 7.9
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0525/ML052500501.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.8
CFR Part: 
CFR Title: 

Content:
1. 10 CFR Parts 50 and 52 a. 50.55a(a)(1) Quality Standards for Systems Important to Safety A A A A A A A A b. 50.55a(h) Criteria for Protection Systems for Nuclear Power Generating Stations (ANSI/IEEE Std 279) A A * * * * * ** c. 50.34(f)(2)(v) [I.D.3] Bypass and Inoperable Status Indication A A A A ** See NUREG-0718, -0737, -0737 Supplement 1, and -0694 d. 50.34(f)(2)(xii) [II.E.1.2] Auxiliary Feedwater System Automatic Initiation and Flow Indication A A Applies only to PWRs. See NUREG-0718, -0737, and -0694 e. 50.34(f)(2)(xvii) [II.F.1] Accident Monitoring Instrumentation A See NUREG-0718, -0737 Supplement 1, and -0694 f. 50.34(f)(2)(xviii) [II.F.2] Inadequate Core Cooling Instrumentation A See NUREG-0694 g. 50.34(f)(2)(xiv) [II.E.4.2] Containment Isolation Systems A See NUREG-0737 h. 50.34(f)(2)(xix) [II.F.3] Instruments for Monitoring Plant Conditions Following Core Damage A See NUREG-0718 i. 50.34(f)(2)(xx) [II.G.1] Power for Pressurizer Level Indication and Controls for Pressurizer Relief and Block Valves A A Applies only to PWRs. See NUREG-0737 j. 50.34(f)(2)(xxii) [II.K.2.g] Failure Mode and Effect Analysis of Integrated Control System A Applies only to B&W plants. See NUREG- 0718, -0737, and -0694 k. 50.34(f)(2) (xxiii)(II.K.2.10) Anticipatory Trip on Loss of Main Feedwater or Turbine Trip A Applies only to B&W plants. See NUREG- 0737, and -0694 Rev. 4 — June 1997 SRP T7.1-3 Criteria Title Applicability Remarks