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Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition — Transient and Accident Analysis (NUREG-0800, Chapter 15)
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| 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 Thursday, August 27, 2026
Page Last Reviewed/Updated Thursday, August 27, 2026