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Course: Senior Reactor Operator Management Certification (SRO-9)

Course Code: Course Name:
SRO-9 Senior Reactor Operator Management Certification
Course ID: Course Duration:
N/A 9.0 Week(s)

Description:

The Senior Reactor Operator (SRO) Management Certification Course prepares the successful student to direct the operation of the Westinghouse Standardized Nuclear Unit Power Plant Systems (SNUPPS) plant under normal, abnormal, and emergency plant conditions.  This course is intended for nuclear power plant managers, supervisors, and personnel requiring integrated plant system and operational knowledge.  The following pre-requisite knowledge is required for success in this course:

  • Introductory-level knowledge of Pressurized Water Reactor (PWR) fundamentals, systems, and operation
  • Basic math skills including logarithms and algebraic manipulation of equations
  • Human Performance Fundamentals

Consistent with the Nuclearning® Educational Model, the Senior Reactor Operator Management Certification Course incorporates numerous student-centered learning activities to help the student learn and remember the concepts being studied. This approach puts the student at the center of the learning process making him an active participant in all learning activities. Specifically, the course incorporates classroom exercises, control board demonstrations, group work exercises, student presentations, and hands-on main control room simulator operation.  Industry operating events are incorporated throughout the course to provide context for the knowledge and skills acquired, and to keep nuclear safety in the forefront of all system and personnel interactions.

The Senior Reactor Operator Management Certification Course is nine (9) weeks in length. A typical course is made up of one (1) operating team, but can accommodate up to two (2) teams.  Since hands-on learning in the simulator control room is an integral part of the course, the recommended number of students for each operating team is five (5).

The maximum number of students for this course is ten (10).


Course Schedule:

      Week 1 – Classroom

  • Introduction to the Reactor Coolant System
  • Introduction to Graphic Language and Logic
  • Reactor Vessel Internals
  • Reactor Physics
  • Excore and Incore Nuclear Instrumentation
  • Temperature Instrumentation
  • Pressurizer System
  • Core and Primary System Thermodynamics
  • Steam and Turbine Systems
  • Condensate and Feedwater
  • Weekly Examination

     

    Week 2 – Classroom

  • Introduction to Technical Specifications
  • Chemical and Volume Control System
  • Neutron Kinetics
  • Control Reactivity
  • Reactor Makeup System
  • Intrinsic Reactivity
  • Rod Control System
  • Secondary System Thermodynamics
  • Reactor Coolant Pumps
  • Weekly Examination
  • Weekly Examination

     

    Week 3 – Classroom

  • Reactor Protection System
  • Core Design Limits
  • Steam Generators and Level Control System
  • Turbine Electro-Hydraulic Control System
  • Steam Dump System
  • Turbine Auxiliaries
  • Main Generation
  • Generator Auxiliaries
  • Service Water and Circulating Water Systems
  • Component Cooling Water System
  • Safeguards Power and Standby Power Systems
  • Service DC and Instrument Power
  • Weekly Examination

     

    Week 4 – Classroom

  • Residual Heat Removal System
  • Engineered Safety Features
  • Emergency Core Cooling System
  • Auxiliary Feedwater System
  • Safeguard Systems Integrated Operations
  • Subcritical Multiplication
  • Reactor Startup
  • Systems and Theory Review
  • Final Systems and Fundamentals Examination

     

    Week 5 – Classroom/Simulator

  • Power Operations – Load Changes
  • Outage Overview
  • Tour Waltz Mill Equipment and Mock-up Bays
  • Reactor Shutdown
  • Plant Cooldown and Depressurization
  • Establishing a Pressurizer Bubble
  • Plant Startup
  • Reactor Startup
  • Power Increase to 100% Power
  • Weekly Examination

     

     Week 6 – Classroom/Simulator

  • Power Operations – Load Changes
  • Individual Reactor Startups
  • Abnormal Operating Procedures
    • Load Rejections
    • Turbine Trip
    • Nuclear Instrument System Malfunctions
    • Steam Generator Level Malfunctions
    • RCS RTD Malfunctions
    • Emergency Boration
  • Emergency Operating Procedures
    • Reactor Trip Response
  • Weekly Examination

     

    Week 7 – Classroom/Simulator

  • Power Operations – Load Changes
  • Abnormal Operating Procedures – Malfunctions:
    • Pressurizer Level and Pressure
    • Reactor Coolant System Leakage
  • Emergency Operating Procedures
    • Reactor Trip/Safety Injection (SI) Response
    • SI Termination
    • Loss of Coolant Accident
    • Steamline Break
    • Feedwater Break
  • Emergency Plan/Classification
  • Critical Safety Functions
  • Weekly Examination

     

    Week 8 – Classroom/Simulator

  • Power Operations – Load Changes
  • Functional Restoration Guidelines
    • Anticipated Transient Without SCRAM (ATWS)
  • Abnormal Operating Procedures – Malfunctions:
    • Steam Generator Tube Leak
    • Rapid Load Reduction
  • Emergency Operating Procedures
    • Steam Generator Tube Rupture
    • Loss of All AC
    • Pressurizer Steam Space Break
  • Practice Simulator Scenarios
  • Weekly Examination

     

    Week 9 – Classroom/Simulator

  • Practice Simulator Exam Scenarios
  • Final SRO Written Examination
  • Final Simulator Operational Examination

Target Audience:
This course is intended for nuclear power plant managers, supervisors, and personnel requiring integrated plant system and operational knowledge.

Technology Requirements:

Computer access for access to online course materials, work, and examinations


Satisfactory Completion Requirements:
80% or greater on program written examinations and satisfactory completion of all performance evaluations, including final comprehensive written examination and simulator operational examinations.

Learning Objectives:
Upon completion of this training, the successful student will have the knowledge and skills required to direct the operation of the Westinghouse Standardized Nuclear Unit Power Plant Systems (SNUPPS) plant under normal, abnormal, and emergency plant conditions.

Prerequisites:

The following pre-requisite knowledge is required for success in this course:

  • Introductory-level knowledge of Pressurized Water Reactor (PWR) fundamentals, systems, and operation
  • Basic math skills including logarithms and algebraic manipulation of equations
  • Human Performance Fundamentals

Cancellation Policy:

All registrations are subject to a 100% cancellation charge if not cancelled more than 20 business days prior to the class start date. This policy also applies to "no shows". 

If class minimum is not met, course will be cancelled one month prior to scheduled start date.

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