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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 |
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021