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 |