The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition — Transient and Accident Analysis (NUREG-0800, Chapter 15)

This page includes links to files in non-HTML format. See Plugins, Viewers, and Other Tools for more information.

Section Title Rev. Date Updated
15.0 Introduction - Transient and Accident Analyses Draft Rev. 4 07/2023
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 03/2007
Initial Issuance 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

* For new license applications see SRP Section 15.0.3.
** The technical content has been relocated to Branch Technical position 11.6.

Page Last Reviewed/Updated Tuesday, October 3, 2023