United States Nuclear Regulatory Commission - Protecting People and the Environment

Design-Specific Review Standard (DSRS) for the mPower™ Design - Chapter 15

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NUREG-0800 SRP/DSRS Section No. NUREG-0800 SRP/DSRS Section Title Applicability of NUREG-0800 Section to mPower™ Design Comments/Additional Guidance Documents to be used for Review, etc.
15.0
ML12275A026
Introduction - Transient and Accident Analyses C) Modify SRP Section for DSRS  
15.0.1 Radiological Consequence Analyses Using Alternate Source Terms B) Delete SRP Section for DSRS (N/A)  
15.0.2
ML12207A098
Review of Transient and Accident Analysis Methods C) Modify SRP Section for DSRS  
15.0.3
ML12257A226
Design Basis Accident Radiological Consequence Analyses for Advanced Light Water Reactors C) Modify SRP Section for DSRS  
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 C) Modify SRP Section for DSRS This section to be released for public comment via separate FRN at a later date.
15.1.5
ML12207A108
Steam System Piping Failures Inside and Outside of Containment C) Modify SRP Section for DSRS  
15.1.5.A Radiological Consequences of Main Steam Line Failures Outside Containment of a PWR B) Delete SRP Section for DSRS (N/A)  
15.2.1 - 15.2.5
ML12319A584
Loss of External Load; Turbine Trip; Loss of Condenser Vacuum; Closure of Main Steam Isolation Valve (BWR); and Steam Pressure Regulator Failure (Closed) C) Modify SRP Section for DSRS  
15.2.6
ML12319A587
Loss of Nonemergency AC Power to the Station Auxiliaries C) Modify SRP Section for DSRS  
15.2.7
ML12250A248
Loss of Normal Feedwater Flow C) Modify SRP Section for DSRS  
15.2.8
ML12319A668
Feedwater System Pipe Breaks Inside and Outside Containment (PWR) C) Modify SRP Section for DSRS  
15.3.1 - 15.3.2
ML12319A585
Loss of Forced Reactor Coolant Flow Including Trip of Pump Motor and Flow Controller Malfunctions C) Modify SRP Section for DSRS  
15.3.3 - 15.3.4
ML12319A586
Reactor Coolant Pump Rotor Seizure and Reactor Coolant Pump Shaft Break C) Modify SRP Section for DSRS  
15.4.1
ML12240A005
Uncontrolled Control Rod Assembly Withdrawal from a Subcritical or Low Power Startup Condition C) Modify SRP Section for DSRS  
15.4.2
ML12242A102
Uncontrolled Control Rod Assembly Withdrawal at Power C) Modify SRP Section for DSRS  
15.4.3
ML063600415
Control Rod Misoperation (System Malfunction or Operator Error) A) Use SRP Section "as-is" (minor comments)  
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 B) Delete SRP Section for DSRS (N/A)  
15.4.6 Inadvertent Decrease in Boron Concentration in the Reactor Coolant System (PWR) B) Delete SRP Section for DSRS (N/A)  
15.4.7
ML070550013
Inadvertent Loading and Operation of a Fuel Assembly in an Improper Position A) Use SRP Section "as-is" (minor comments)  
15.4.8 Spectrum of Rod Ejection Accidents (PWR) B) Delete SRP Section for DSRS (N/A)  
15.4.8.A Radiological Consequences of a Control Rod Ejection Accident (PWR) B) Delete SRP Section for DSRS (N/A)  
15.4.9 Spectrum of Rod Drop Accidents (BWR) B) Delete SRP Section for DSRS (N/A)  
15.4.9.A Radiological Consequences of Control Rod Drop Accident (BWR) B) Delete SRP Section for DSRS (N/A)  
15.4.10
ML12261A399
Startup of an Inactive Pump or Pumps at an Incorrect Temperature, and Flow Controller Malfunction causing an Increase in Core Flow Rate D) Develop new DSRS Section  
15.5.1 - 15.5.2
ML12319A575
Inadvertent Operation of ECCS and Reactor Coolant Inventory and Purification System (RCI) Malfunction that Increases Reactor Coolant Inventory C) Modify SRP Section for DSRS  
15.6.1
ML12250A318
Inadvertent Opening of a Pressurizer Safety Valve, or an Automatic Depressurization Valve C) Modify SRP Section for DSRS  
15.6.2 Radiological Consequences of the Failure of Small Lines Carrying Primary Coolant Outside Containment B) Delete SRP Section for DSRS (N/A)  
15.6.3 Radiological Consequences of Steam Generator Tube Failure (PWR) B) Delete SRP Section for DSRS (N/A)  
15.6.4 Radiological Consequences of Main Steam Line Failure Outside Containment (BWR) B) Delete SRP Section for DSRS (N/A)  
15.6.5
ML12319A576
Loss of Coolant Accidents Resulting From Spectrum of Postulated Piping Breaks Within the Reactor Coolant Pressure Boundary C) Modify SRP Section for DSRS  
15.6.5.A Radiological Consequences of a Design Basis Loss-of-Coolant Accident Including Containment Leakage Contribution B) Delete SRP Section for DSRS (N/A)  
15.6.5.B Radiological Consequences of a Design Basis Loss-of-Coolant Accident Leakage From Engineered Safety Feature Components Outside Containment B) Delete SRP Section for DSRS (N/A)  
15.6.5.D Radiological Consequences of a Design Basis Loss-of-Coolant Accident: Leakage From Main Steam Isolation Valve Leakage Control System (BWR) B) Delete SRP Section for DSRS (N/A)  
15.7.3 Postulated Radioactive Releases Due to Liquid-Containing Tank Failures B) Delete SRP Section for DSRS (N/A)  
15.7.4 Radiological Consequences of Fuel Handling Accidents B) Delete SRP Section for DSRS (N/A)  
15.7.5 Spent Fuel Cask Drop Accidents B) Delete SRP Section for DSRS (N/A)  
15.8
ML12319A577
Anticipated Transients Without Scram C) Modify SRP Section for DSRS  
15.9 Boiling Water Reactor Stability B) Delete SRP Section for DSRS (N/A)  
15.9.A
ML12261A042
Thermal Hydraulic Stability D) Develop new DSRS Section  
Page Last Reviewed/Updated Tuesday, May 14, 2013