StandardReview Plan for the Review of Safety Analysis Reports for Nuclear Power Plants:LWR Edition — Reactor (NUREG-0800, Chapter 4)
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| Section |
Title |
Rev. |
Date Updated |
| 4.2 |
Fuel System Design |
Rev. 3 |
03/2007 |
| Draft Rev. 3 |
06/1996 |
| Rev. 2 |
07/1981 |
| Rev. 1 |
09/1978 |
| Rev. 0 |
11/1975 |
| 4.3 |
Nuclear Design |
Rev. 3 |
03/2007 |
| Draft Rev. 3 |
06/1996 |
| Rev. 2 |
07/1981 |
| Rev. 1 |
04/1978 |
| Rev. 0 |
11/1975 |
| 4.4 |
Thermal and Hydraulic Design |
Rev. 2 |
03/2007 |
| Draft Rev. 2 |
06/1996 |
| Rev. 1 |
07/1981 |
| Rev. 0 |
11/1975 |
| 4.5.1 |
Control Rod Drive Structural Materials |
Rev. 3 |
03/2007 |
| Draft Rev. 3 |
06/1996 |
| Rev. 2 |
07/1981 |
| Rev. 1 |
01/1978 |
| Rev. 0 |
11/1975 |
| 4.5.2 |
Reactor Internal and Core Support Structure Materials |
Rev. 3 |
03/2007 |
| Draft Rev. 3 |
06/1996 |
| Rev. 2 |
07/1981 |
| Rev. 1 |
01/1978 |
| Rev. 0 |
11/1975 |
| 4.6 |
Functional Design of Control Rod Drive System |
Rev. 2 |
03/2007 |
| Draft Rev. 2 |
06/1996 |
| Rev. 1 |
07/1981 |
| Rev. 0 |
11/1975 |
| |
Branch Technical Position (BTP) |
|
|
| BTP 4-1 |
Westinghouse Constant Axial Offset Control (CAOC) (Former Section 4.3 BTP has been separated into an individual section.) |
Rev. 3 |
03/2007 |