Section |
Title |
Rev. |
Date Updated |
15 |
Introduction - Transient and Accident Analyses |
Rev.
3 |
03/2007 |
Draft
Rev. 3 |
06/1996 |
Rev.
2 |
07/1981 |
Rev. 1 |
08/1978 |
Rev. 0 |
11/1975 |
15.0.1 |
Radiological Consequence Analyses Using Alternative Source Terms
|
Rev.
0 |
07/2000 |
15.0.2 |
Review of Transient and Accident Analysis Method |
Rev.
0 |
12/2005 |
Draft
Rev. 0 |
01/2003 |
15.0.3 |
Design Basis Accident Radiological Consequences of Analyses for
Advanced Light Water Reactors |
Initial
Issuance |
03/2007 |
15.1.1 - 15.1.4 |
Decrease in Feedwater Temperature, Increase in Feedwater
Flow, Increase in Steam Flow, and Inadvertent Opening of a Steam Generator
Relief or Safety Valve |
Rev.
2 |
03/2007 |
Draft
Rev. 2 |
06/1996 |
Rev.
1 |
07/1981 |
Rev. 0 |
11/1975 |
15.1.5 |
Steam System Piping Failures Inside and Outside of Containment
(PWR) |
Rev.
3 |
03/2007 |
Draft
Rev. 3 |
06/1996 |
Rev.
2 |
07/1981 |
Rev. 1 |
08/1978 |
Rev. 0 |
11/1975 |
15.1.5.A* |
Radiological Consequences of Main Steam Line Failures
Outside Containment of a PWR |
Rev.
2 |
07/1981 |
Rev.
1 |
08/1978 |
Rev. 0 |
11/1975 |
15.2.1 - 15.2.5 |
Loss of External Load; Turbine Trip; Loss of Condenser
Vacuum; Closure of Main Steam Isolation Valve (BWR); and Steam Pressure
Regulator Failure (Closed) |
Rev.
2 |
03/2007 |
Draft
Rev. 2 |
06/1996 |
Rev.
1 |
07/1981 |
Rev. 0 |
11/1975 |
15.2.6 |
Loss of Nonemergency AC Power to the Station Auxiliaries
|
Rev.
2 |
03/2007 |
Draft
Rev. 2 |
06/1996 |
Rev.
1 |
07/1981 |
Rev. 0 |
11/1975 |
15.2.7 |
Loss of Normal Feedwater Flow |
Rev.
2 |
03/2007 |
Draft
Rev. 2 |
06/1996 |
Rev. 1 |
07/1981 |
Rev. 0 |
11/1975 |
15.2.8 |
Feedwater System Pipe Breaks Inside and Outside Containment
(PWR) |
Rev.
2 |
03/2007 |
Draft
Rev. 2 |
06/1996 |
Rev.
1 |
07/1981 |
Rev. 0 |
11/1975 |
15.3.1 - 15.3.2 |
Loss of Forced Reactor Coolant Flow Including Trip of
Pump Motor and Flow Controller Malfunctions |
Rev.
2 |
03/2007 |
Draft
Rev. 2 |
06/1996 |
Rev.
1 |
07/1981 |
Rev. 0 |
11/1975 |
15.3.3 - 15.3.4 |
Reactor Coolant Pump Rotor Seizure and Reactor Coolant
Pump Shaft Break |
Rev.
3 |
03/2007 |
Draft
Rev. 3 |
06/1996 |
Rev.
2 |
07/1981 |
Rev. 1 |
08/1978 |
Rev. 0 |
11/1975 |
15.4.1 |
Uncontrolled Control Rod Assembly Withdrawal from a
Subcritical or Low Power Startup Condition |
Rev.
3 |
03/2007 |
Draft
Rev. 3 |
06/1996 |
Rev.
2 |
07/1981 |
Rev. 1 |
04/1978 |
Rev. 0 |
11/1975 |
15.4.2 |
Uncontrolled Control Rod Assembly Withdrawal at Power |
Rev.
3 |
03/2007 |
Draft
Rev. 3 |
06/1996 |
Rev. 2 |
07/1981 |
Rev. 1 |
04/1978 |
Rev. 0 |
11/1975 |
15.4.3 |
Control Rod Misoperation (System Malfunction or Operator
Error) |
Rev.
3 |
03/2007 |
Draft
Rev. 3 |
06/1996 |
Rev.
2 |
07/1981 |
Rev. 1 |
04/1978 |
Rev. 0 |
11/1975 |
15.4.4 - 15.4.5 |
Startup of an Inactive Loop or Recirculation Loop at
an Incorrect Temperature, and Flow Controller Malfunction Causing
an Increase in BWR Core Flow Rate |
Rev.
2 |
03/2007 |
Draft
Rev. 2 |
06/1996 |
Rev.
1 |
07/1981 |
Rev. 0 |
11/1975 |
15.4.6 |
Inadvertent Decrease in Boron Concentration in the Reactor
Coolant System (PWR) |
Rev.
2 |
03/2007 |
Draft
Rev. 2 |
06/1996 |
Rev.
1 |
07/1981 |
Rev. 0 |
11/1975 |
15.4.7 |
Inadvertent Loading and Operation of a Fuel Assembly
in an Improper Position |
Rev.
2 |
03/2007 |
Draft
Rev. 2 |
06/1996 |
Rev.
1 |
07/1981 |
Rev. 0 |
11/1975 |
15.4.8 |
Spectrum of Rod Ejection Accidents (PWR) |
Rev.
3 |
03/2007 |
Draft
Rev. 3 |
06/1996 |
Rev.
2 |
07/1981 |
Rev. 1 |
04/1978 |
Rev. 0 |
11/1975 |
15.4.8.A |
Radiological Consequences of a Control Rod Ejection
Accident (PWR) |
Rev.
1 |
07/1981 |
Rev. 0 |
11/1975 |
15.4.9 |
Spectrum of Rod Drop Accidents (BWR) |
Rev.
3 |
03/2007 |
Draft
Rev. 3 |
06/1996 |
Rev.
2 |
07/1981 |
Rev. 1 |
04/1978 |
Rev. 0 |
11/1975 |
15.4.9.A* |
Radiological Consequences of Control Rod Drop Accident
(BWR) |
Rev. 2 |
07/1981 |
Rev. 1 |
04/1978 |
Rev. 0 |
11/1975 |
15.5.1 - 15.5.2 |
Inadvertent Operation of ECCS and Chemical and Volume
Control System Malfunction that Increases Reactor Coolant Inventory
|
Rev.
2 |
03/2007 |
Draft
Rev. 2 |
06/1996 |
Rev.
1 |
07/1981 |
Rev. 0 |
11/1975 |
15.6.1 |
Inadvertent Opening of a PWR Pressurizer Pressure Relief
Valve or a BWR Pressure Relief Valve |
Rev.
2 |
03/2007 |
Draft
Rev. 2 |
04/1996 |
Rev.
1 |
07/1981 |
15.6.2* |
Radiological Consequences of the Failure of Small Lines Carrying Primary Coolant Outside Containment |
Rev.
2 |
07/1981 |
Rev. 1 |
07/1978 |
Rev. 0 |
11/1975 |
15.6.3* |
Radiological Consequences of Steam Generator Tube Failure
|
Rev. 2 |
07/1981 |
Rev. 1 |
12/1978 |
Rev. 0 |
11/1975 |
15.6.4* |
Radiological Consequences of Main Steam Line Failure
Outside Containment (BWR) |
Rev. 2 |
07/1981 |
Rev. 1 |
07/1978 |
Rev. 0 |
11/1975 |
15.6.5 |
Loss-of-Coolant Accidents Resulting From Spectrum of
Postulated Piping Breaks Within the Reactor Coolant Pressure Boundary
|
Rev.
3 |
03/2007 |
Draft
Rev. 3 |
06/1996 |
Rev.
2 |
07/1981 |
Rev. 1 |
08/1978 |
Rev. 0 |
11/1975 |
15.6.5.A* |
Radiological Consequences of a Design Basis Loss-of-Coolant Accident Including Containment Leakage Contribution |
Rev. 1 |
07/1981 |
Rev. 0 |
11/1975 |
15.6.5.B* |
Radiological Consequences of a Design Basis Loss-of-Coolant Accident: Leakage From Engineered Safety Feature Components Outside Containment |
Rev. 1 |
07/1981 |
Rev. 0 |
11/1975 |
15.6.5.D* |
Radiological Consequences of a Design Basis Loss-of-Coolant
Accident: Leakage From Main Steam Isolation Valve Leakage Control System (BWR) |
Rev. 1 |
07/1981 |
Rev. 0 |
11/1975 |
15.7.3** |
Postulated Radioactive Releases Due to Liquid-Containing Tank Failures |
Rev. 2 |
07/1981 |
Rev. 1 |
07/1978 |
Rev. 0 |
11/1975 |
15.7.4* |
Radiological Consequences of Fuel Handling Accidents
|
Rev.
1 |
07/1981 |
Rev. 0 |
11/1975 |
15.7.5* |
Spent Fuel Cask Drop Accidents |
Rev. 2 |
07/1981 |
Rev. 1 |
12/1978 |
Rev. 0 |
11/1975 |
15.8 |
Anticipated Transients Without Scram |
Rev.
2 |
03/2007 |
Rev.
1 |
07/1981 |
Rev. 0 |
11/1975 |
15.9 |
Boiling Water Reactor Stability |
Initial
Issuance |
03/2007 |