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StandardReview Plan for the Review of Safety Analysis Reports for Nuclear Power Plants:LWR Edition — Engineered Safety Features (NUREG-0800,Chapter 6)

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Section Title Rev. Date Updated
6.1.1 Engineered Safety Features Materials Rev. 2 03/2007
Draft Rev. 2 06/1996
Rev. 2 07/1981
Rev. 1 12/1978
Rev. 0 11/1975
6.1.2 Protective Coating Systems (Paints) - Organic Materials Rev. 3 03/2007
Draft Rev. 3 06/1996
Rev. 2 07/1981
Rev. 1 12/1978
Rev. 0 11/1975
6.2.1 Containment Functional Design Rev. 3 03/2007
Draft Rev. 3 06/1996
Rev. 2 07/1981
Rev. 1 04/1978
Rev. 0 11/1975
6.2.1.1.A PWR Dry Containments, Including Subatmospheric Containments Rev. 3 03/2007
Draft Rev. 3 06/1996
Rev. 2 07/1981
Rev. 1 08/1978
Rev. 0 11/1975
6.2.1.1.B Ice Condenser Containments Draft Rev. 3 06/1996
Rev. 2 07/1981
Rev. 1 08/1978
Rev. 0 11/1975
6.2.1.1.C Pressure-Suppression Type BWR Containments Rev. 7 03/2007
Draft Rev. 7 06/1996
Rev. 6 08/1984
Rev. 5 01/1983
Rev. 4 07/1981
Rev. 3 02/1979
Rev. 2 08/1978
Rev. 1 05/1978
Rev. 0 11/1975
6.2.1.2 Subcompartment Analysis Rev. 3 03/2007
Draft Rev. 3 06/1996
Rev. 2 07/1981
Rev. 1 08/1978
Rev. 0 11/1975
6.2.1.3 Mass and Energy Release Analysis for Postulated Loss-of-Coolant Accidents (LOCAs) Rev. 3 03/2007
Rev. 2 01/2006
Draft Rev. 2 06/1996
Rev. 1 07/1981
Rev. 0 11/1975
6.2.1.4 Mass and Energy Release Analysis for Postulated Secondary System Pipe Ruptures Rev. 2 03/2007
Draft Rev. 2 06/1996
Rev. 1 07/1981
Rev. 0 11/1975
6.2.1.5 Minimum Containment Pressure Analysis for Emergency Core Cooling System Performance Capability Studies Rev. 3 03/2007
Draft Rev. 3 06/1996
Rev. 2 07/1981
Rev. 1 08/1978
Rev. 0 11/1975
6.2.2 Containment Heat Removal Systems Rev. 5 03/2007
Draft Rev. 5 06/1996
Rev. 4 10/1985
Rev. 3 07/1981
Rev. 2 08/1978
Rev. 1 04/1978
Rev. 0 11/1975
6.2.3 Secondary Containment Functional Design Rev. 3 03/2007
Draft Rev. 3 06/1996
Rev. 2 07/1981
Rev. 1 08/1978
Rev. 0 11/1975
6.2.4 Containment Isolation System Rev. 3 03/2007
Draft Rev. 3 06/1996
Rev. 2 07/1981
Rev. 1 05/1978
Rev. 0 11/1975
6.2.5 Combustible Gas Control in Containment Rev. 3 03/2007
Draft Rev. 3 06/1996
Rev. 2 07/1981
Rev. 1 05/1978
Rev. 0 11/1975
6.2.6 Containment Leakage Testing Rev. 3 03/2007
Draft Rev. 3 06/1996
Rev. 2 07/1981
Rev. 1 09/1978
Rev. 0 11/1975
6.2.7 Fracture Prevention of Containment Pressure Boundary Rev. 1 03/2007
Draft Rev. 1 06/1996
Rev. 0 07/1981
6.3 Emergency Core Cooling System Rev. 3 03/2007
Draft Rev. 3 06/1996
Rev. 2 04/1984
Rev. 1 07/1981
Rev. 0 11/1975
6.4 Control Room Habitability System Rev. 3 03/2007
Draft Rev. 3 06/1996
Rev. 2 07/1981
Rev. 1 12/1978
Rev. 0 11/1975
6.5.1 ESF Atmosphere Cleanup Systems Rev. 4 05/2010
Rev. 3 03/2007
Draft Rev. 3 06/1996
Rev. 2 07/1981
Rev. 1 07/1978
Rev. 0 11/1975
6.5.2 Containment Spray as a Fission Product Cleanup System Rev. 4 03/2007
Rev. 3 12/2005
Draft Rev. 3 06/1996
Rev. 2 12/1988
Rev. 1 07/1981
Rev. 0 11/1975
6.5.3 Fission Product Control Systems and Structures Rev. 3 03/2007
Draft Rev. 3 06/1996
Rev. 2 07/1981
Rev. 1 07/1978
Rev. 0 11/1975
6.5.4 Ice Condenser as a Fission Product Cleanup System Draft Rev. 4 06/1996
Rev. 3 12/1988
Rev. 2 07/1981
Rev. 1 04/1978
Rev. 0 11/1975
6.5.5 Pressure Suppression Pool as a Fission Product Cleanup System Rev. 1 03/2007
Draft Rev. 1 06/1996
Rev. 0 12/1988
6.6 Inservice Inspection and Testing of Class 2 and 3 Components Rev. 2 03/2007
Draft Rev. 2 06/1996
Rev. 1 07/1981
Rev. 0 11/1975
6.7 Main Steam Isolation Valve Leakage Control System (BWR) Draft Rev. 3 06/1996
Rev. 2 07/1981
Rev. 1 03/1978
Rev. 0 11/1975
  Branch Technical Positions (BTPs)    
BTP 6-1 pH For Emergency Coolant Water for Pressurized Water Reactors Initial Issuance 03/2007
BTP 6-2 Minimum Containment Pressure Model for PWR ECCS Performance Evaluation (Former Section 6.2.1.5 BTP has been separated into an individual section.) Rev. 3 03/2007
BTP 6-3 Determination of Bypass Leakage Paths in Dual Containment Plants (Former Section 6.2.3 BTP has been separated into an individual section.) Rev. 3 03/2007
BTP 6-4 Containment Purging During Normal Plant Operations (Former Section 6.2.4 BTP has been separated into an individual section.) Rev. 3 03/2007
BTP 6-5 Currently the Responsibility of Reactor Systems Piping From the RWST (or BWST) and Containment Sump(s) to the Safety Injection Pumps (Former Section 6.3 BTP has been separated into an individual section.) Rev. 3 03/2007
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