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Home NRC Library Document Collections NUREG-Series Publications Publications Prepared by NRC Staff NUREG-0800

StandardReview Plan for the Review of Safety Analysis Reports for Nuclear Power Plants:LWR Edition — Reactor Coolant System and Connected Systems (NUREG-0800,Chapter 5)

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Section Title Rev. Date Updated
5.2.1.1 Compliance with the Codes and Standards Rule, 10 CFR 50.55a Rev. 4 12/2016
Draft Rev. 4 08/2015
Rev. 3 03/2007
Draft Rev. 3 06/1996
Rev. 2 07/1981
Rev. 1 01/1978
Rev. 0 11/1975
5.2.1.2 Applicable Code Cases Rev. 4 12/2016
Draft Rev. 4 08/2015
Rev. 3 03/2007
Draft Rev. 3 06/1996
Rev. 2 07/1981
Rev. 1 01/1978
Rev. 0 11/1975
5.2.2 Overpressure Protection Rev. 3 03/2007
Draft Rev. 3 06/1996
Rev. 2 11/1988
Rev. 1 07/1981
Rev. 0 11/1975
5.2.3 Reactor Coolant Pressure Boundary Materials Rev. 3 03/2007
Draft Rev. 3 06/1996
Rev. 2 07/1981
Rev. 1 04/1978
Rev. 0 11/1975
5.2.4 Reactor Coolant Pressure Boundary Inservice Inspection and Testing Rev. 2 03/2007
Draft Rev. 2 06/1996
Rev. 1 07/1981
Rev. 0 11/1975
5.2.5 Reactor Coolant Pressure Boundary Leakage Detection Rev. 2 03/2007
Draft Rev. 2 06/1996
Rev. 1 07/1981
Rev. 0 11/1975
5.3.1 Reactor Vessel Materials Rev. 2 03/2007
Draft Rev. 2 06/1996
Rev. 1 07/1981
Rev. 0 11/1975
5.3.2 Pressure-Temperature Limits, Upper-Shelf Energy, and Pressurized Thermal Shock Rev. 2 03/2007
Draft Rev. 2 06/1996
Rev. 1 07/1981
Rev. 0 11/1975
5.3.3 Reactor Vessel Integrity Rev. 2 03/2007
Draft Rev. 2 06/1996
Rev. 1 07/1981
Rev. 0 11/1975
5.4 Reactor Coolant System Component and Subsystem Design Rev. 2 03/2007
Draft Rev. 2 06/1996
Rev. 1 07/1981
Rev. 0 11/1975
5.4.1.1 Pump Flywheel Integrity (PWR) Rev. 3 05/2010
Rev. 2 03/2007
Draft Rev. 2 06/1996
Rev. 1 07/1981
Rev. 0 11/1975
5.4.2.1 Steam Generator Materials and Design Rev. 4 07/2016
Draft Rev. 4 04/2016
Rev. 3 03/2007
Draft Rev. 3 06/1996
Rev. 2 07/1981
Rev. 1 11/1978
Rev. 0 11/1975
5.4.2.2 Steam Generator Program Rev. 2 03/2007
Draft Rev. 2 06/1996
Rev. 1 07/1981
Rev. 0 11/1975
5.4.6 Reactor Core Isolation Cooling System (BWR) Rev. 4 03/2007
Draft Rev. 4 06/1996
Rev. 3 04/1984
Rev. 2 07/1981
Rev. 1 03/1978
Rev. 0 11/1975
5.4.7 Residual Heat Removal (RHR) System Rev. 5 05/2010
Rev. 4 03/2007
Draft Rev. 4 06/1996
Rev. 3 04/1984
Rev. 2 07/1981
Rev. 1 08/1978
Rev. 0 11/1975
5.4.8 Reactor Water Cleanup System (BWR) Rev. 3 03/2007
Draft Rev. 3 06/1996
Rev. 2 07/1981
Rev. 1 07/1978
Rev. 0 11/1975
5.4.11 Pressurizer Relief Tank Rev. 4 05/2010
Rev. 3 03/2007
Draft Rev. 3 06/1996
Rev. 2 07/1981
Rev. 1 08/1978
Rev. 0 11/1975
5.4.12 Reactor Coolant System High Point Vents Rev. 1 03/2007
Draft Rev. 1 06/1996
Rev. 0 07/1981
5.4.13 Isolation Condenser System (BWR) Initial Issuance 03/2007
  Branch Technical Positions (BTPs)    
BTP 5-1 Monitoring of Secondary Side Water Chemistry in PWR Steam Generators (Former Section 5.4.2.1 BTP has been separated into an individual section.) Rev. 3 03/2007
BTP 5-2 Overpressurization Protection of Pressurized-Water Reactors While Operating at Low Temperatures (Former Section 5.2.2 BTP has been separated into an individual section.) Rev. 3 03/2007
BTP 5-3 Fracture Toughness Requirements Rev. 3 07/2018
Rev. 2 03/2007
BTP 5-4 Design Requirements of the Residual Heat Removal System Rev. 4 03/2007

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