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This course plan, its lessons and its assessments has not yet been verified by a licensed professional engineer or master tradesperson or by a certification or approval body. It is a study draft and may contain errors. Do not use it as instructions for work on a job site or on live equipment. Always follow your instructor, your supervising professional, and current official references and regulations.

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Nuclear Power Plant Technician / Operator Prep

11 courses · 3,600 clock hours · 12–24 mo full-time. Grading is competency-based: each course requires the written exam, a competent skills demonstration with zero safety faults, a signed log, and a passed safety audit; percentage weights only rank performance above the competency floor.

$55,275 COMPLIMENTARYprogram tuition
11courses
103lessons
3,600hours
39assessments
Development progressPlanCourses, lessons and assessments written for this tradeLessons103 of 103 lesson pages writtenPractice820 practice questionsResources117 reference entries (study list)Review0 lesson pages reviewed by a licensed professional
Study now: 103 lesson pages are open (lesson titles below are links).
BLD-NUCL84-01 Universal core

Universal Core: Safety, Math, Communication & Career for Nuclear Power Plant Technicians

148 hr · $1,185 COMPLIMENTARY

This foundational course equips adult learners with the safety protocols, technical mathematics, communication skills, and career readiness knowledge required to enter nuclear power plant training programs and succeed in subsequent coursework. Students earn OSHA 10 certification and first aid/CPR credentials while building the quantitative and literacy skills demanded by NRC-regulated worksites. All content is calibrated to the nuclear utility environment, from radiation-aware PPE decisions to reading plant technical specifications.

Outcomes
Course text

This foundational course equips adult learners with the safety protocols, technical mathematics, communication skills, and career readiness knowledge required to enter nuclear power plant training programs and succeed in subsequent coursework. Students earn OSHA 10 certification and first aid/CPR credentials while building the quantitative and literacy skills demanded by NRC-regulated worksites. All content is calibrated to the nuclear utility environment, from radiation-aware PPE decisions to reading plant technical specifications.

How the course runs. 7 blocks: Nuclear Workplace Hazard Recognition and OSHA 10 General Industry; Lockout/Tagout, PPE Selection, and First Aid/CPR; Technical Mathematics for Nuclear Plant Work; Reading Technical Documents: Procedures, Drawings, and Specifications; Digital Tools for Nuclear Plant Technicians; Nuclear Safety Culture and Professional Communication; Career Pathways, Credentials, and Personal Development Planning.

What competent looks like. Complete OSHA 10 General Industry training and demonstrate correct hazard identification, lockout/tagout procedures, and PPE selection for nuclear plant environments. Apply arithmetic, algebra, unit conversion, and basic statistics to solve plant-relevant measurement and calculation problems with at least 80% accuracy. Read and interpret technical documents—including procedures, material safety data sheets, and simplified plant drawings—using active-reading strategies appropriate to nuclear operations. Use standard digital tools (spreadsheets, plant computerized maintenance management system concepts, and electronic work orders) to record, organize, and communicate technical data. Demonstrate professional communication in written reports, verbal briefings, and three-way communication drills consistent with nuclear safety culture expectations. Articulate the career pathways from non-licensed operator to licensed Reactor Operator, identify the credentials required at each stage, and construct a personal career development plan.

Lessons · 7 blocks
#LessonHrTypeObjectiveActivitiesMaterialsCheck
1Nuclear Workplace Hazard Recognition and OSHA 10 General Industry12theoryStudents will identify the major OSHA General Industry hazard categories present on a nuclear power plant site and complete all OSHA 10 Outreach Program modules required for card issuance.
  1. Work through all OSHA 10 General Industry modules delivered by an authorized OSHA Outreach trainer, completing the required sign-in sheets and end-of-module quizzes.
  2. Review a simplified nuclear plant site map and classify visible hazards (electrical, chemical, fall, struck-by, ergonomic, and radiological awareness) by OSHA category, recording findings on a structured worksheet.
  3. Participate in a guided discussion comparing OSHA General Industry standards with additional NRC-specific access and posting requirements for radiologically controlled areas, noting where OSHA rules are the baseline minimum.
OSHA 10 General Industry student booklets (authorized trainer-supplied), plant site map handout, OSHA 29 CFR 1910 reference summary card, whiteboard, projector.Completion of all OSHA 10 modules with attendance verified by authorized trainer; students pass the OSHA 10 final assessment at the threshold set by the Outreach program to qualify for card submission. Classroom worksheet scores 80% or higher.
2Lockout/Tagout, PPE Selection, and First Aid/CPR16labStudents will correctly perform a six-step lockout/tagout sequence on a simulated multi-energy-source equipment station and demonstrate first aid and CPR skills to the standard required for certification.
  1. Observe an instructor demonstration of a complete LOTO procedure on a training board with simulated electrical, pneumatic, and hydraulic energy isolation points; then each student performs the full sequence independently and is observed by a peer using a step-by-step checklist.
  2. Select appropriate PPE (hard hat class, safety glasses, gloves, hearing protection, and respiratory protection type) for three written nuclear plant scenario cards—one involving electrical work, one involving chemical contact risk, and one in a posted radiologically controlled area—justifying each choice in writing.
  3. Complete an American Heart Association or American Red Cross Heartsaver First Aid/CPR/AED course including hands-on mannequin practice, two-rescuer CPR, AED trainer use, and hemorrhage control, culminating in the certification skills test.
LOTO training board with multiple energy isolation points, assorted locks and tags, LOTO procedure instruction card, PPE selection scenario cards, full PPE kit samples, CPR mannequins, AED trainer, first aid kit, AHA or ARC Heartsaver course materials.LOTO checklist: all six steps performed in correct sequence with zero critical errors (skipping verification step = automatic fail); PPE scenario justification scored on rubric, 80% minimum; CPR/First Aid: pass skills station to AHA/ARC certification standard.
3Technical Mathematics for Nuclear Plant Work30practiceStudents will solve problems involving unit conversion, scientific notation, algebraic equations, ratios, percentages, and basic statistics as applied to nuclear plant instrumentation readings, flow rates, and dose calculations.
  1. Complete a sequenced problem set that begins with SI and US customary unit conversions (temperature in Fahrenheit, Celsius, and Kelvin; pressure in psi and pascals; flow in gallons per minute and liters per second), progressing to multi-step problems that combine conversions with algebraic formulas drawn from plant contexts such as heat balance and dilution.
  2. Work through a scientific notation and significant-figures drill using actual orders of magnitude encountered in nuclear work (reactor power in watts, radioactive decay constants, coolant chemistry concentrations), then peer-check answers against an instructor key.
  3. Analyze a small data set of simulated daily reactor power-output readings using mean, range, and standard deviation calculations; present findings as a written summary paragraph with a hand-drawn trend chart, practicing the kind of shift-log entry expected of a plant technician.
Scientific calculators (non-programmable), unit conversion reference card, instructor-prepared problem sets aligned to NEI NUCP mathematics competency areas, graph paper, plant operations context examples handout.Scored problem set: 80% overall with no more than one error in unit-conversion problems (unit errors in plant work can have safety consequences). Statistics summary paragraph evaluated on rubric for numerical accuracy and clear written explanation.
4Reading Technical Documents: Procedures, Drawings, and Specifications24theoryStudents will apply active-reading strategies to extract specific technical information from nuclear plant operating procedures, one-line electrical diagrams, piping and instrumentation diagram symbols, and equipment specification sheets.
  1. Using a sample plant operating procedure (simplified for training), annotate the document for purpose, prerequisites, caution/warning statements, action steps, and acceptance criteria, then answer a set of comprehension questions that require locating specific data in the document.
  2. Identify standard P&ID symbols (valves, pumps, heat exchangers, instrumentation tags) on a training-level piping and instrumentation diagram excerpt; complete a symbol-matching exercise and trace the flow path of a described process from source to destination.
  3. Read two equipment specification sheets (one for a pump, one for a sensor) and complete a structured data-extraction form asking for rated operating parameters, required maintenance intervals noted in the document, and any stated cautions—then compare findings with a partner and resolve discrepancies.
Sample nuclear plant operating procedure (training version, cleared for classroom use), P&ID symbol legend reference (ISA standard symbols overview), training P&ID excerpt, two equipment specification sheet handouts, active-reading annotation guide.Procedure comprehension quiz: 80% minimum. P&ID symbol exercise: 85% symbol identification accuracy. Spec-sheet extraction form: all required fields completed with accurate values; any blank field is flagged for review with instructor before lesson close.
5Digital Tools for Nuclear Plant Technicians20demoStudents will use spreadsheet software to organize equipment data and perform calculations, and describe the purpose and basic workflow of a computerized work-order and maintenance-management system as used in nuclear plant operations.
  1. Follow a step-by-step instructor demonstration of spreadsheet fundamentals (data entry, formulas, cell referencing, basic charting), then independently complete a guided exercise that replicates a plant log-sheet: entering simulated instrument readings, calculating averages with formulas, and generating a bar chart of daily values.
  2. Watch an instructor walkthrough of a training-mode computerized maintenance management system (CMMS) interface or a realistic simulation thereof; identify the major sections (work-order creation, equipment history, parts lookup, approval workflow) and record their functions in a structured note-taking template.
  3. Draft a sample electronic corrective-action document for a simulated equipment deficiency (a gauge reading outside its expected band), following a provided template that mirrors nuclear plant condition-reporting practices, and submit for instructor feedback.
Computers or tablets with spreadsheet software, instructor-prepared spreadsheet exercise file, CMMS training interface or realistic simulator screen captures, electronic work-order template, projector for demonstration.Spreadsheet exercise checked against answer key: correct formulas and chart type, 80% accuracy. CMMS note template: all five major sections correctly identified and described. Condition-report draft: evaluated on rubric for completeness, factual accuracy, and use of neutral/precise language; must meet all required fields.
6Nuclear Safety Culture and Professional Communication30practiceStudents will demonstrate three-way communication, pre-job briefing participation, and a written shift-log entry consistent with the NRC's safety culture framework and nuclear industry communication standards.
  1. Study the NRC's published safety culture components and the Institute of Nuclear Power Operations (INPO) traits of a healthy nuclear safety culture; in small groups, analyze three brief scenario cards depicting communication failures that contributed to real (anonymized) nuclear industry events, identifying which safety-culture trait was violated and what the correct behavior should have been.
  2. Practice three-way communication (initiator states message, receiver repeats back, initiator confirms or corrects) in pairs using a series of escalating plant-context messages—valve positions, instrument readings, alarm announcements—until each student achieves two consecutive error-free exchanges observed by the instructor.
  3. Participate in a simulated pre-job briefing for a routine maintenance task as either the briefing leader or a crew member; the leader uses a provided briefing checklist (task scope, hazards, stop-work authority, critical steps), and all participants practice raising a concern using the plant's questioning attitude protocol before writing a one-paragraph shift-log entry summarizing the activity.
NRC Safety Culture Policy Statement summary handout, INPO safety culture traits reference, scenario analysis cards, three-way communication drill cards, pre-job briefing checklist template, shift-log entry template.Scenario analysis: group written responses evaluated on rubric—correct trait identification and evidence-based justification, 80% minimum. Three-way communication drill: instructor observes and marks pass/fail per exchange; must achieve two consecutive error-free exchanges. Pre-job briefing and shift-log entry: rubric-scored on completeness and safety-culture alignment, 80% minimum.
7Career Pathways, Credentials, and Personal Development Planning16fieldStudents will construct a written personal career development plan that maps the credentials required for advancement from non-licensed operator to NRC-licensed Reactor Operator, identifying the utility-sponsorship requirement and the role of each program credential.
  1. Attend a structured panel Q&A with two or three nuclear industry professionals (invited in person or via video conference) representing roles such as non-licensed operator, radiation protection technician, and licensed reactor operator; students prepare and submit at least three written questions in advance and take structured notes on career progression, wage expectations, and advice for new entrants.
  2. Using a provided credential-mapping worksheet, locate each program credential (OSHA 10, NRRPT, NUCP, NRC Non-Licensed Operator Prep, NRC Reactor Operator License) on a career-stage timeline, annotating the purpose of each, who grants it, whether utility sponsorship is required, and the typical sequence in which workers obtain them.
  3. Draft a personal career development plan of at least one full page that states the student's target role at five years, the credentials needed, an action step for each credential, any prerequisite education or experience gaps identified, and one specific professional organization or resource the student will use for ongoing development.
Career pathway timeline handout, credential-mapping worksheet, panel guest contact arrangements, notepad for panel notes, personal career plan template, program credential fact sheets.Credential-mapping worksheet: all five credentials correctly placed on timeline with accurate annotations, instructor-verified. Personal career plan: evaluated on four-point rubric (goal clarity, credential accuracy, actionability, professional tone); minimum score of 3 out of 4 on each dimension to pass.
Assessments
AssessmentTypeWeightPass standardMethod & rubric
OSHA 10 and Workplace Safety Knowledge ExamWritten exam25%Score of 70% or higher on the OSHA Outreach program's required assessment to qualify for card submission; 80% or higher on the supplemental nuclear site safety quiz.A two-part written examination covering OSHA General Industry hazard categories, LOTO procedures, PPE selection rationale, and nuclear-specific posting and access requirements. Part one is administered by the authorized OSHA Outreach trainer per program requirements; part two is a 25-item instructor-written quiz on nuclear site safety context. Maps to the OSHA 10 credential requirement.
Accuracy · Safety · Communication · Professionalism
Technical Math and Document Literacy ExamWritten exam25%80% overall; unit-conversion section requires 80% with no more than one error; document comprehension section requires 80%.A 50-item written exam covering unit conversion, scientific notation, algebraic problem-solving, basic statistics, and reading comprehension of a short operating procedure excerpt and a P&ID symbol set. Problems are drawn from nuclear plant contexts and are representative of the mathematics and literacy demands in the NEI NUCP Uniform Curriculum competency framework.
Accuracy · Safety · Communication · Professionalism
Digital Tools and Communication Portfolio ProjectProject25%Rubric total of 80% or higher across all four sections; any section scoring below 60% must be revised and resubmitted within one week.Students submit a portfolio containing: a completed and accurately formatted spreadsheet log with chart, a filled-in CMMS workflow summary, a drafted condition-report document, and a written shift-log entry. The portfolio demonstrates integration of digital tool skills with nuclear safety-culture communication standards and is evaluated by the instructor using a four-section rubric.
Accuracy · Safety · Communication · Professionalism
Career Plan Oral DefenseOral / panel25%Score of 3 out of 4 or higher on each of the four rubric dimensions (goal clarity, credential knowledge, personal action steps, communication professionalism); any dimension scored 1 requires a remediation meeting and revised submission.Each student presents their personal career development plan to the instructor and one peer in a 10-minute structured oral defense, explaining the credential pathway from non-licensed operator to licensed Reactor Operator, justifying their target role, and responding to at least two follow-up questions. This assessment measures the oral communication, safety-culture, and career-readiness outcomes of the course.
Accuracy · Safety · Communication · Professionalism
BLD-NUCL84-02 Trade course

Reactor Physics & Thermodynamics

314 hr · $6,500 COMPLIMENTARY

This course builds the foundational nuclear science and thermodynamic principles that govern commercial light-water reactor operation. Students progress from atomic structure and neutron behavior through reactor kinetics, heat transfer, and the thermodynamic cycles used in pressurized-water and boiling-water reactor plants. Mastery of these principles is required for NRC Non-Licensed Operator and Reactor Operator license preparation, the NUCP Uniform Curriculum, and NRRPT radiation protection fundamentals.

Outcomes
Course text

This course builds the foundational nuclear science and thermodynamic principles that govern commercial light-water reactor operation. Students progress from atomic structure and neutron behavior through reactor kinetics, heat transfer, and the thermodynamic cycles used in pressurized-water and boiling-water reactor plants. Mastery of these principles is required for NRC Non-Licensed Operator and Reactor Operator license preparation, the NUCP Uniform Curriculum, and NRRPT radiation protection fundamentals.

How the course runs. 12 blocks: Atomic Structure, Radioactive Decay, and Nuclear Reactions; Neutron Interactions and Cross Sections; Fission Chain Reaction and Criticality — The Six-Factor Formula; Reactor Kinetics: Prompt and Delayed Neutrons, Reactor Period; Reactivity Coefficients and Feedback Mechanisms; Control Rods, Chemical Shim, and Reactivity Control Systems; Xenon and Samarium Poisoning — Fission Product Effects; Heat Transfer Fundamentals — Conduction and Convection in Reactor Systems; Reactor Coolant System Thermodynamics — Pressure, Temperature, and Phase Behavior of Water; The Rankine Cycle and Nuclear Plant Power Conversion; Integrated Plant Behavior — Coupling Neutronics and Thermal-Hydraulics; Reactor Physics & Thermodynamics Review and NRC Exam Alignment.

What competent looks like. Explain nuclear fission, chain reaction criticality, and the six-factor formula in terms that predict reactor behavior during power changes. Apply reactor kinetics concepts—including reactivity coefficients, delayed neutrons, and reactor period—to describe transient plant conditions qualitatively and quantitatively. Describe the thermodynamic cycle (Rankine cycle) of a light-water reactor plant, tracing energy conversion from fuel to turbine-generator output. Calculate basic heat transfer quantities (conduction, convection, heat flux) relevant to fuel cladding integrity and primary coolant behavior. Identify how moderator temperature, void fraction, fuel temperature, and boron concentration affect reactivity, and state the safety significance of each. Interpret plant parameter trends on simplified reactor diagrams and predict the direction and magnitude of reactivity change for normal and off-normal events.

Lessons · 12 blocks
#LessonHrTypeObjectiveActivitiesMaterialsCheck
1Atomic Structure, Radioactive Decay, and Nuclear Reactions20theoryStudents will describe the structure of the atom, distinguish the major decay modes, write balanced nuclear reactions, and explain how fission releases energy.
  1. Lecture and annotated diagram exercise: students label protons, neutrons, electrons, and identify isotopes of uranium and plutonium on a nuclide chart; quiz on atomic number versus mass number.
  2. Decay-mode card sort: given a set of cards describing alpha, beta-minus, beta-plus, gamma, and neutron emission, students match each to its penetrating ability, shielding requirement, and biological hazard—connecting directly to NRRPT and OSHA 10 PPE selection.
  3. Worked-problem set: students balance six nuclear equations (including U-235 fission and neutron capture reactions), check mass-energy equivalence using E=mc², and present one solution to the class for peer critique.
Nuclide chart (Knolls Atomic Power Laboratory edition or equivalent), Lamarsh & Baratta 'Introduction to Nuclear Engineering' (3rd ed.), scientific calculators, whiteboard, decay-mode reference cardsScored 10-question quiz on atomic notation and decay modes; pass mark 80%. Students must correctly balance at least 5 of 6 nuclear equations to advance.
2Neutron Interactions and Cross Sections24theoryStudents will explain how neutrons interact with matter (scatter, absorption, fission), define macroscopic and microscopic cross sections, and use the concept to compare moderator and fuel neutron behavior.
  1. Instructor-led lecture with energy-spectrum diagrams: students trace a fast neutron from fission through slowing-down to thermal energies, annotating interactions at each stage on a printed 1/v cross-section graph.
  2. Cross-section comparison worksheet: using tabulated values for hydrogen, oxygen, U-235, U-238, and boron-10, students calculate mean free path for thermal neutrons in water and explain why light water is an effective moderator and why boron is used for reactivity control.
  3. Small-group analogy exercise: groups build a simple probabilistic model (dice-roll simulation) to illustrate the statistical nature of neutron absorption versus scattering, then present findings and connect to why reactor power is predictable despite individual randomness.
Printed thermal cross-section tables (ENDF/B data, instructor-summarized), graph paper, scientific calculators, Lamarsh & Baratta textbook, whiteboardTwo-part check: (1) students correctly define and distinguish microscopic vs. macroscopic cross section in writing; (2) correctly calculate mean free path for at least 3 of 4 given scenarios. Pass mark 80%.
3Fission Chain Reaction and Criticality — The Six-Factor Formula28theoryStudents will define each factor in the six-factor formula (η, ε, p, f, P_TNL, P_FNL), state how each is controlled in a light-water reactor, and calculate the effective multiplication factor k-eff for simplified cases.
  1. Structured note-taking lecture: instructor derives the six-factor formula step by step; students maintain a running definition table and record which plant system or mechanism controls each factor.
  2. k-eff sensitivity exercise: using a simplified spreadsheet model (instructor-provided), students vary one factor at a time (e.g., increase absorption fraction f by adding boron) and record the effect on k-eff, then explain in one sentence the physical meaning of each change.
  3. Criticality scenario discussion: instructor presents three written reactor scenarios (fuel loading, normal operation, xenon transient) and student teams must determine whether the reactor is subcritical, critical, or supercritical, citing the controlling factor and its physical basis; teams present reasoning to class.
Instructor-provided spreadsheet (Excel or Google Sheets), scientific calculators, printed six-factor formula reference sheet, whiteboard, Lamarsh & Baratta textbookWritten scenario analysis: given two reactor conditions, student must correctly classify k-eff state and identify the dominant contributing factor. Pass mark 80% (at least 4 of 5 questions correct).
4Reactor Kinetics: Prompt and Delayed Neutrons, Reactor Period28theoryStudents will distinguish prompt from delayed neutrons, explain why delayed neutrons make reactor control possible, and calculate approximate reactor period from reactivity insertion using the inhour equation in simplified form.
  1. Lecture with timeline diagrams: students annotate a fission event timeline showing prompt neutron emission (~10⁻¹⁴ s) versus delayed neutron emission (up to ~55 s), then explain in writing why a reactor controlled only by prompt neutrons would be uncontrollable at normal reactivity levels.
  2. Delayed neutron group table exercise: using a standard six-group delayed neutron data table for U-235, students calculate the weighted mean delayed neutron fraction (β) and compare to the prompt criticality threshold, reinforcing the concept of 'prompt critical' as an operational boundary to avoid.
  3. Reactor period calculation practice: students use the simplified inhour approximation to compute reactor period for three given reactivity insertions (small positive, near-prompt-critical, and small negative), plot power vs. time on semi-log paper, and identify which case represents an unacceptable transient.
Delayed neutron group data table (U-235, Keepin values), semi-log graph paper, scientific calculators, Lamarsh & Baratta textbook, whiteboardProblem set of five reactor period calculations; students must correctly compute period and classify reactor behavior (stable, period alarm, prompt critical approach) for each. Pass mark 80%.
5Reactivity Coefficients and Feedback Mechanisms28theoryStudents will define and apply the moderator temperature coefficient, void coefficient, and fuel temperature (Doppler) coefficient, and explain why a negative overall power coefficient is required for safe reactor operation.
  1. Lecture with cause-and-effect mapping: students build a written cause-and-effect chain for each coefficient (e.g., power increase → fuel temperature rise → Doppler broadening → increased U-238 resonance absorption → negative reactivity → power stabilizes), reinforcing the self-regulating nature of properly designed LWRs.
  2. Coefficient sign analysis worksheet: instructor presents eight reactor parameter change scenarios; students determine sign (positive or negative) of the resulting reactivity feedback and state whether that feedback aids or opposes stability—connecting to NRC regulations requiring negative power coefficients.
  3. Boiling-water reactor void coefficient case study: using a simplified BWR diagram, students trace how increased steam void fraction changes neutron moderation and reactivity, compare to a PWR, and write a one-paragraph safety significance summary for each design.
BWR and PWR simplified system diagrams (NEI or plant-generic training materials), printed worksheet, whiteboard, scientific calculators, Lamarsh & Baratta textbookOral check: each student must verbally explain one assigned coefficient, give the sign for a standard LWR, and state its safety significance to instructor satisfaction. Written backup: 10-question quiz at 80% pass mark.
6Control Rods, Chemical Shim, and Reactivity Control Systems22demoStudents will describe how control rods and boron chemical shim (PWR) or control rods alone (BWR) are used to control reactor power and shutdown margin, and identify the reactivity worth concepts involved.
  1. Instructor demonstration using a simplified reactor physics simulator (PC-based IAEA PCTRAN or equivalent free-access educational tool): instructor inserts and withdraws control rods while students observe power, period, and temperature response, recording observations in a structured data table.
  2. Boron dilution/addition calculation exercise: students calculate the approximate change in boron concentration (in ppm) needed to compensate a given reactivity change (instructor-provided simplified worth data), reinforcing the chemical shim concept used in PWR operation.
  3. Control rod worth curve sketching: students sketch a typical S-shaped control rod differential worth curve from given data points, label the region of maximum differential worth (rod at core midplane), and explain in writing why rod position matters for reactivity insertion rate.
PC-based reactor simulator (IAEA PCTRAN or equivalent educational tool), printed control rod worth data table, graph paper, scientific calculators, generic PWR/BWR training manualsLab data table reviewed by instructor: all observations correctly recorded and all three boron calculations within 10% of instructor answer. Students must correctly interpret one simulator transient in writing. Pass mark 80%.
7Xenon and Samarium Poisoning — Fission Product Effects24theoryStudents will explain how xenon-135 and samarium-149 build up and decay in an operating reactor, predict xenon oscillation behavior after a power reduction, and state the operational significance of xenon peak after shutdown.
  1. Lecture with production/decay chain diagrams: students trace the Te-135 → I-135 → Xe-135 → Cs-135 chain and the Pm-149 → Sm-149 chain, annotating half-lives and production rates from fission, then calculate equilibrium Xe-135 concentration at full power using simplified instructor-provided equations.
  2. Xenon transient plot exercise: using pre-calculated data from a standard xenon transient table (instructor-provided), students plot xenon worth vs. time following a 50% power reduction and a full shutdown, identify the xenon peak time and magnitude, and explain why the reactor may not be restartable during the peak.
  3. Operational scenario discussion: instructor presents the Three Mile Island Unit 1 xenon oscillation historical context (operations training context only, not accident); students discuss how xenon spatial oscillations can occur in large cores and what axial flux monitoring is designed to detect.
Printed xenon transient data tables, semi-log graph paper, scientific calculators, generic nuclear plant operations training text (Westinghouse AP1000 or generic PWR training manual excerpt), whiteboardWritten response: student must correctly draw a xenon peak curve after shutdown, label time to peak, and explain in two sentences why the reactor cannot be restarted during the peak. Plus 5-question quiz at 80% pass mark.
8Heat Transfer Fundamentals — Conduction and Convection in Reactor Systems28theoryStudents will apply Fourier's law of conduction and Newton's law of cooling to calculate temperature gradients across fuel pellets, cladding, and coolant, and explain how these gradients determine fuel centerline temperature limits.
  1. Lecture with cross-section diagram of a fuel rod: students label fuel pellet, gap, cladding, and coolant regions, then apply Fourier's law to calculate temperature drop across the cladding for a given heat flux, using instructor-provided thermal conductivity values.
  2. Multi-layer thermal resistance worksheet: students treat the fuel rod as a series of thermal resistances (pellet → gap → cladding → coolant), calculate the temperature at each interface for a given linear heat rate, and compare fuel centerline temperature to a generic melting point limit to determine acceptability.
  3. Convection coefficient comparison exercise: students compare natural vs. forced convection heat transfer coefficients for reactor coolant, explain why forced circulation is critical at power, and describe what occurs during a loss-of-flow event in terms of heat transfer—connecting to DNBR (departure from nucleate boiling ratio) as a safety limit.
Printed thermal property tables (conductivity, specific heat for UO₂, Zircaloy, water at operating conditions), scientific calculators, ruler, pencils, generic nuclear plant thermal analysis reference (Todreas & Kazimi 'Nuclear Systems' or instructor excerpts)Problem set of four fuel rod temperature calculation problems; students must set up and solve each correctly, with final temperatures within 5% of answer key. Pass mark: 3 of 4 correct (75% minimum, rounded to 80% with partial credit rubric).
9Reactor Coolant System Thermodynamics — Pressure, Temperature, and Phase Behavior of Water28theoryStudents will use steam tables and the pressure-temperature saturation curve to determine the state of reactor coolant, explain subcooled margin, and describe what happens to primary coolant if pressure drops unexpectedly.
  1. Steam table navigation exercise: instructor distributes printed steam tables; students look up saturation temperature for ten given pressures spanning reactor operating range (approximately atmospheric to PWR operating pressure), then plot the saturation curve and label the subcooled, two-phase, and superheated regions.
  2. Subcooled margin calculation worksheet: given typical PWR primary system pressure and measured coolant temperature, students calculate the subcooled margin (saturation temperature minus actual temperature) and determine whether coolant is adequately subcooled for safe single-phase operation.
  3. Phase transition scenario analysis: students are given four plant scenarios (normal operation, pressurizer low-pressure alarm, loss-of-coolant accident initiation, safety injection) and must determine the coolant phase state at the core inlet for each, justifying their answer using the saturation curve—directly supporting RO license exam content on thermal margins.
Printed steam tables (International Steam Tables or equivalent), printed blank P-T saturation curve template, scientific calculators, whiteboard, generic PWR/BWR thermal-hydraulics training manualSteam table quiz: 8 lookup and calculation questions; students must correctly determine saturation temperature, enthalpy, or subcooled margin for each. Pass mark 80%. Instructor checks phase-state reasoning on two scenarios verbally.
10The Rankine Cycle and Nuclear Plant Power Conversion30theoryStudents will trace the complete Rankine thermodynamic cycle for a nuclear steam supply system, calculate thermal efficiency for a simplified cycle using given enthalpies, and describe the function of each major component (steam generator/reactor, turbine, condenser, feedwater heaters, pumps).
  1. Rankine cycle diagram construction: students draw a complete PWR or BWR power conversion cycle from memory after instructor presentation, labeling state points (1–4 minimum), enthalpy values from steam tables, and naming each process (isentropic expansion, condensation, isentropic compression, constant-pressure heat addition).
  2. Thermal efficiency calculation exercise: using instructor-provided enthalpy values at four cycle state points, students calculate turbine work output, pump work input, heat added, and overall thermal efficiency; compare result to a generic nuclear plant efficiency range and explain losses (moisture separator, reheater needs).
  3. Component function worksheet: students complete a table matching each component (pressurizer, steam generator, high-pressure turbine, moisture separator-reheater, condenser, feedwater heater, condensate/feedwater pumps) to its thermodynamic function, working fluid state change, and the plant system it belongs to—bridging to Course 3 (Plant Systems).
Printed steam tables, Rankine cycle blank T-s and h-s diagram templates, scientific calculators, whiteboard, generic PWR and BWR power conversion system diagrams (NEI NUCP training materials or plant-generic)Completed Rankine cycle diagram with correct labels and one numerical efficiency calculation checked against answer key within 3%. Pass mark: diagram 80% complete and efficiency within acceptable tolerance.
11Integrated Plant Behavior — Coupling Neutronics and Thermal-Hydraulics34labStudents will use a PC-based educational reactor simulator to demonstrate how changes in coolant temperature, pressure, and flow interact with neutron flux and reactivity feedback in real time, and document observed plant responses in a structured lab log.
  1. Simulator lab session 1 — power increase transient: each student (or pair) starts the simulator at 50% power, initiates a controlled power increase by withdrawing control rods, and records neutron flux, reactor period, fuel temperature, coolant outlet temperature, and pressurizer pressure at 1-minute intervals until 100% power is reached; they must identify all feedback effects observed.
  2. Simulator lab session 2 — feedwater flow reduction: students reduce feedwater flow rate by a specified amount, observe steam generator level and secondary steam pressure changes, then trace how steam generator pressure change feeds back to primary coolant temperature and reactivity; they predict the direction of power change before running the transient and check their prediction against the simulator output.
  3. Lab log completion and analysis: each student writes a structured lab log entry for both transients following a provided template (objective, procedure, data tables, observations, analysis questions, conclusion); analysis questions require students to cite specific reactivity coefficients and heat transfer principles from earlier lessons to explain each observed trend.
PC workstations with IAEA PCTRAN or equivalent educational nuclear simulator installed, printed lab log template, scientific calculators, student notes from lessons 1–9Instructor reviews completed lab log against answer guide: data tables complete, at least 80% of analysis questions answered correctly with correct physical reasoning, no unsupported conclusions. Simulator performance observed in real time; students must correctly predict transient direction before running each scenario.
12Reactor Physics & Thermodynamics Review and NRC Exam Alignment20practiceStudents will identify gaps in their knowledge across all course topics, practice NRC-style multiple choice and written response questions mapped to the Non-Licensed Operator and Reactor Operator exam content areas, and develop a personal study plan for certification exam preparation.
  1. Timed practice exam: students complete a set of NRC-style questions covering atomic physics, criticality, kinetics, reactivity coefficients, xenon, heat transfer, steam tables, and the Rankine cycle; instructor grades and returns with itemized feedback mapped to specific lesson objectives and credential exam content areas (NUCP categories and NRC exam domains).
  2. Targeted small-group review sessions: based on practice exam results, instructor groups students by weakness area (e.g., steam tables, six-factor formula, delayed neutrons) and facilitates focused 20-minute review stations with worked examples, students rotating through each station.
  3. Personal study plan development: each student reviews their practice exam performance data, selects three priority review topics, writes a one-page study plan listing specific resources (textbook sections, simulator practice scenarios, formula cards) and target review dates leading into the Course 11 Exam Prep course.
Instructor-prepared NRC-style question bank (aligned to NUCP Uniform Curriculum and NRC exam content outlines), formula reference sheet, student notes and lab logs, whiteboard, printed study plan templatePractice exam score recorded as a formative baseline (no minimum pass required at this stage, but scores below 70% trigger mandatory instructor conference and study plan review). Personal study plan submitted and reviewed by instructor for completeness.
Assessments
AssessmentTypeWeightPass standardMethod & rubric
Reactor Physics & Thermodynamics Knowledge ExaminationWritten exam25%80% or higher on a 50-question written examination; any question involving a safety-critical calculation (DNBR margin, subcooled margin, prompt critical boundary) must be answered correctly regardless of overall score.A closed-book, timed written examination covering atomic structure, neutron interactions, the six-factor formula, reactor kinetics, reactivity coefficients, fission product poisoning, heat transfer, steam tables, and the Rankine cycle. Questions include multiple-choice, fill-in, and short calculation items aligned to NRC Non-Licensed Operator and Reactor Operator license content areas and the NEI NUCP Uniform Curriculum domains.
Standard met · Safety · Time · Quality/finish · Documentation
Simulator Transient Analysis Skills DemonstrationSkills demonstration45%Student must correctly predict the direction of all key parameter changes before each transient run, execute the procedure without safety limit violations on the simulator, and provide an acceptable verbal explanation (judged by instructor using a standardized rubric) of all observed feedback mechanisms; rubric requires 80% of criteria met.Each student individually operates the educational reactor simulator to execute a prescribed transient (power ramp or reactivity insertion), records data, and provides a real-time verbal explanation of neutron kinetics and thermal-hydraulic feedback to the instructor. The demonstration directly maps to NRC Reactor Operator license competency areas for understanding plant response to reactivity changes.
Standard met · Safety · Time · Quality/finish · Documentation
Laboratory Log PortfolioLog15%All required lab log entries submitted; each entry must achieve 80% or higher on the instructor scoring rubric covering data completeness, accuracy of analysis questions, correct application of physical principles, and quality of conclusions.Students submit a complete portfolio of their structured lab log entries from the integrated plant behavior simulator lab (Lesson 11) and all calculation worksheets from heat transfer and steam table lessons. The portfolio demonstrates the student's ability to collect, record, and interpret quantitative plant data — a skill directly required for non-licensed operator daily logs and supporting NRRPT documentation practices.
Standard met · Safety · Time · Quality/finish · Documentation
Reactivity Control and Thermal Margin Safety CheckSafety audit15%100% correct identification of all safety-critical conditions presented; any missed unsafe condition (subcooling loss, prompt critical approach, DNBR limit exceedance) results in automatic failure and mandatory remediation before course credit is awarded.The instructor presents five written plant-parameter scenarios; the student must classify each as safe, requiring operator action, or requiring immediate shutdown (scram), citing the specific physical principle (subcooled margin, prompt critical boundary, fuel temperature limit, or DNBR) that governs the decision. This safety check confirms that students can correctly apply course content to protect plant safety — a non-negotiable competency for NRC-licensed and non-licensed operator roles.
Standard met · Safety · Time · Quality/finish · Documentation
BLD-NUCL84-03 Trade course

Nuclear Plant Systems

313 hr · $6,480 COMPLIMENTARY

This course provides a comprehensive study of the major mechanical, fluid, electrical, and auxiliary systems found in light-water reactor nuclear power plants, including pressurized-water reactor (PWR) and boiling-water reactor (BWR) configurations. Students trace energy flow from the reactor core through the primary and secondary systems to the turbine-generator and balance-of-plant equipment, learning normal operating parameters, system interactions, and failure modes. Content directly supports the NRC Non-Licensed Operator and Reactor Operator license exam areas, the NUCP Uniform Curriculum plant systems modules, and the NRRPT knowledge base for system-related radiological hazards.

Outcomes
Course text

This course provides a comprehensive study of the major mechanical, fluid, electrical, and auxiliary systems found in light-water reactor nuclear power plants, including pressurized-water reactor (PWR) and boiling-water reactor (BWR) configurations. Students trace energy flow from the reactor core through the primary and secondary systems to the turbine-generator and balance-of-plant equipment, learning normal operating parameters, system interactions, and failure modes. Content directly supports the NRC Non-Licensed Operator and Reactor Operator license exam areas, the NUCP Uniform Curriculum plant systems modules, and the NRRPT knowledge base for system-related radiological hazards.

How the course runs. 12 blocks: Introduction to Plant Systems Architecture and Energy Flow; Reactor Coolant System: PWR Primary Loop; Reactor Coolant System: BWR Primary System and Recirculation; Secondary System: Steam, Turbine, and Condenser; Feedwater and Condensate Systems; Engineered Safety Feature Systems: Emergency Core Cooling; Containment Systems and Containment Isolation; Electrical Power Systems: Normal and Emergency AC/DC; Auxiliary Systems: Component Cooling Water, Service Water, and HVAC; Plant System Drawings and P&ID Interpretation Lab; Normal and Off-Normal System Evolutions: Operator Response; Integrated System Interactions and Plant Transient Analysis.

What competent looks like. Describe the function, major components, and normal operating parameters of the primary coolant system for both PWR and BWR plant designs. Trace the flow path of the secondary system from steam generator or reactor steam dome through turbine, condenser, and feedwater heaters back to the steam generator or reactor vessel. Identify the purpose and operating principles of each engineered safety feature system, including emergency core cooling, containment spray, and auxiliary feedwater systems. Read and interpret plant system drawings including Piping and Instrumentation Diagrams (P&IDs), one-line electrical diagrams, and system flow diagrams to verify system lineup. Apply lockout/tagout procedures and appropriate PPE requirements before performing simulated system lineup and valve manipulation tasks. Recognize and explain off-normal system indications, including high/low pressure alarms, high/low temperature alarms, and flow anomalies, and describe the correct operator response.

Lessons · 12 blocks
#LessonHrTypeObjectiveActivitiesMaterialsCheck
1Introduction to Plant Systems Architecture and Energy Flow20theoryStudents will describe the overall energy conversion pathway from nuclear fission heat to electrical output and identify the major system boundaries in both PWR and BWR plants.
  1. Annotate a large-format cutaway diagram of a PWR and a BWR, labeling each major system boundary, fluid boundary, and energy transfer point with correct nomenclature.
  2. Complete a structured comparison table listing PWR versus BWR differences in primary coolant configuration, steam generation method, containment type, and number of fluid barriers.
  3. Work through a guided energy-balance worksheet tracing thermal megawatts from the reactor core to the generator terminals, identifying where heat is added, transferred, or rejected at each system interface.
NRC Reactor Concepts Manual (NUREG-1082 or current equivalent), NEI NUCP curriculum plant systems module, PWR and BWR cutaway posters, energy balance worksheet, whiteboardStudents correctly label all major system boundaries on a blank plant diagram and complete the energy balance worksheet with no more than one error; pass mark 80%.
2Reactor Coolant System: PWR Primary Loop28theoryStudents will identify the components of the PWR reactor coolant system (RCS), including reactor vessel, reactor coolant pumps, steam generators, and pressurizer, and explain how each component maintains coolant pressure and temperature within licensed limits.
  1. Using a P&ID of a generic PWR RCS, trace the primary coolant flow path loop by loop from the reactor vessel outlet nozzle through each steam generator and reactor coolant pump back to the inlet nozzle, annotating flow direction and approximate operating temperature and pressure ranges.
  2. Analyze a set of normal operating parameter cards for RCS pressure, temperature, flow rate, and pressurizer level, then identify which parameters are controlled automatically and which require manual operator action.
  3. Participate in a structured discussion on the function of the pressurizer heaters and spray nozzles, then sketch and explain the pressure-temperature curve showing the subcooled margin and how operators use it.
Generic PWR RCS P&ID (instructor-prepared, not plant-specific proprietary), NUREG-1082, parameter cards, pressure-temperature curve handout, engineering calculatorStudents trace the correct flow path on an unmarked RCS P&ID and answer a 20-question quiz on component functions and normal parameters; pass mark 80%.
3Reactor Coolant System: BWR Primary System and Recirculation22theoryStudents will explain the BWR single-loop primary system design, describe the function of jet pumps and recirculation pumps, and compare core flow control methods to the PWR approach.
  1. Use a generic BWR flow diagram to trace steam and water separation inside the reactor vessel from the active fuel zone through the steam separators and steam dryers to the main steam lines.
  2. Create a side-by-side outline comparing how power is controlled in a BWR (recirculation flow and control rods) versus a PWR (control rods and chemical shim), identifying the safety significance of each method.
  3. Answer a scenario-based worksheet describing a recirculation pump trip event: students identify the expected plant response, list alarms that would actuate, and state the correct immediate operator actions based on general BWR emergency operating procedure logic.
Generic BWR vessel cutaway diagram, BWR flow diagram, NRC Reactor Concepts Manual, scenario worksheetStudents correctly complete the BWR flow path trace and answer the scenario worksheet with written responses scored against an answer key; pass mark 80%.
4Secondary System: Steam, Turbine, and Condenser26theoryStudents will trace the secondary-side fluid path from the steam generator (or BWR steam dome) through the high-pressure turbine, moisture separator-reheater, low-pressure turbine, and condenser, and describe the thermodynamic function of each component.
  1. Draw a complete secondary system flow diagram from memory after studying a reference diagram, then self-check against the reference and annotate each component with its function and approximate operating condition.
  2. Perform a step-by-step walkthrough of a turbine startup sequence using a generic procedure outline, identifying hold points, key parameter checks, and interlock functions at each step.
  3. Analyze a condenser vacuum problem scenario: given a set of instrument readings (low vacuum, high condenser pressure, elevated condenser hotwell level), students identify probable causes (air in-leakage, condenser tube fouling, loss of circulating water flow) and rank them by likelihood.
Generic secondary system flow diagram, turbine startup procedure outline, condenser scenario data set, steam tables, engineering calculatorStudents reproduce the secondary flow diagram with all major components labeled correctly and score 80% or higher on a 15-question multiple-choice quiz covering thermodynamic functions and operating parameters.
5Feedwater and Condensate Systems22demoStudents will describe the flow path and function of feedwater heaters, deaerator, condensate pumps, and feedwater pumps, and explain how feedwater temperature and flow rate affect reactor power and steam generator level control.
  1. Watch an instructor walkthrough of a generic feedwater system P&ID on the projector, then individually mark up a printed copy identifying each feedwater heater stage (low-pressure and high-pressure), the deaerator, drain paths, and bypass valves.
  2. Calculate the heat transfer improvement achieved by feedwater heating using a simplified enthalpy worksheet, comparing feedwater entering the steam generator at two different temperatures to understand the efficiency benefit.
  3. Role-play as an operator responding to a low steam generator level alarm: use a generic alarm response card to list immediate checks, identify which feedwater pump controls to verify, and state when to escalate to emergency procedures.
Generic feedwater system P&ID, enthalpy worksheet, steam tables, alarm response card template, projectorStudents correctly identify all labeled components on the marked-up P&ID and complete the enthalpy worksheet within 10% of the instructor answer key; pass mark 80% combined.
6Engineered Safety Feature Systems: Emergency Core Cooling30theoryStudents will explain the design basis and actuation logic of emergency core cooling systems (ECCS) including high-pressure injection, low-pressure injection, and accumulator/core flood tank systems for both PWR and BWR designs.
  1. Build a logic chart showing the ECCS actuation signals (low RCS pressure, high containment pressure, low reactor water level) and trace which signal activates which ECCS subsystem, using a generic safety system description document.
  2. Evaluate a loss-of-coolant accident (LOCA) timeline scenario: given a sequence of plant parameter changes over the first ten minutes after a large-break LOCA, students annotate the timeline with expected ECCS actuations and operator actions at each stage.
  3. Participate in a structured Socratic discussion on single-failure criterion: students must explain, in their own words, why ECCS trains are redundant and physically separated, and give one example of how a single active failure could affect system availability.
Generic ECCS system description (instructor-prepared), actuation logic chart template, LOCA timeline scenario worksheet, NRC Reactor Concepts ManualStudents complete the LOCA timeline annotation with no critical safety steps missing and score 80% on a 20-question quiz covering ECCS subsystem functions, actuation signals, and single-failure criterion.
7Containment Systems and Containment Isolation22theoryStudents will describe the design and function of containment structures for PWR (large dry, ice condenser, sub-atmospheric) and BWR (Mark I, II, III) containment types, and explain how containment isolation valves and containment spray systems limit radiological release.
  1. Sketch the basic geometry of at least two containment types (e.g., PWR large-dry and BWR Mark I torus/drywell), label the major barriers, and write a one-paragraph comparison of how each design limits post-accident pressure and temperature.
  2. Work through a containment isolation actuation scenario: given a list of plant parameters indicating a steam line break inside containment, identify which containment isolation group would actuate, which penetrations would close, and which systems remain operable.
  3. Review a generic post-accident containment atmosphere monitoring system description and explain how operators use containment hydrogen concentration readings to determine whether hydrogen igniter or recombiners are needed.
Containment design comparison handout, containment isolation scenario worksheet, generic post-accident monitoring system description, NUREG-0737 overview (as supplemental reading)Students produce correctly labeled containment sketches and score 80% on a 15-question quiz covering containment types, isolation logic, and post-accident control systems.
8Electrical Power Systems: Normal and Emergency AC/DC26theoryStudents will trace the normal offsite and onsite electrical power distribution path from the generator through the main transformer, switchyard, and safety buses, and describe the function of emergency diesel generators and station batteries in a loss of offsite power event.
  1. Using a generic plant one-line electrical diagram, trace power flow from the main generator step-up transformer through the unit auxiliary transformer, startup transformer, 4160-volt safety buses, 480-volt load centers, and 125-volt DC battery buses, labeling each level.
  2. Analyze a loss of offsite power (LOOP) timeline: identify the sequence in which emergency diesel generators start and load, which safety systems are powered first, and what DC battery functions are critical during the first 30 minutes.
  3. Complete a fill-in worksheet on electrical protective devices (breakers, relays, fuses) explaining the protective function of each and what happens to safety-related loads if an emergency bus breaker fails to close.
Generic nuclear plant one-line electrical diagram, LOOP timeline scenario, protective device worksheet, projectorStudents correctly trace and label the one-line diagram and score 80% on a 20-question quiz covering normal and emergency power distribution, diesel generator loading sequence, and battery system function.
9Auxiliary Systems: Component Cooling Water, Service Water, and HVAC20demoStudents will explain the role of component cooling water (CCW), essential service water (ESW), and safety-related HVAC systems as support systems for primary and safety equipment, and describe what happens to supported components if these systems are lost.
  1. Map the heat rejection chain for a reactor coolant pump: trace CCW flow cooling the RCP motor bearing coolers, then trace how CCW transfers heat to service water, and how service water rejects heat to the ultimate heat sink, labeling each heat exchanger.
  2. Evaluate a CCW high-temperature alarm scenario: students list the systems that rely on CCW cooling, prioritize which would be most affected by loss of CCW, and identify what operator actions are required based on a generic alarm response card.
  3. Review a safety-related HVAC system description for an emergency core cooling pump room and explain how the room coolers maintain equipment operability during a design-basis accident, including what happens if room cooling is lost.
Generic CCW/ESW system flow diagram, heat rejection chain worksheet, alarm response card, HVAC system description handoutStudents correctly complete the heat rejection chain map and score 80% on a 10-question quiz on auxiliary system functions, dependencies, and consequences of system loss.
10Plant System Drawings and P&ID Interpretation Lab30labStudents will correctly interpret Piping and Instrumentation Diagrams, one-line electrical diagrams, and system flow diagrams to verify a required system lineup before a simulated evolution, applying lockout/tagout principles to any isolated component.
  1. Using a packet of five generic P&ID segments covering different plant systems, identify and list all hand valves, motor-operated valves, check valves, control valves, instrumentation taps, and pump suctions/discharges on each segment using the correct ISA symbol legend.
  2. Perform a simulated system lineup verification: given a written system lineup checklist for a generic residual heat removal (RHR) system startup, trace each valve position on the P&ID and check it against the checklist, documenting any discrepancy found.
  3. Apply lockout/tagout to a simulated isolated pump using a demonstration lockout station (hasp, locks, tags, LOTO log): students complete the LOTO permit, affix locks and tags to the correct energy isolation points identified on the P&ID, and verify zero energy state per OSHA 29 CFR 1910.147 requirements.
Generic nuclear plant P&ID packet (five segments), ISA symbol legend, RHR system lineup checklist, LOTO demonstration station (hasp, multiple locks, danger tags, LOTO log), OSHA 29 CFR 1910.147 referenceStudents identify all valve and instrument symbols correctly on at least four of five P&ID segments (80% accuracy) and complete the LOTO exercise with zero safety-critical errors; any missed energy isolation point is an automatic fail requiring immediate repeat.
11Normal and Off-Normal System Evolutions: Operator Response35practiceStudents will demonstrate correct use of generic operating procedures and alarm response cards to walk through a normal plant startup evolution and respond to three simulated off-normal system indications without prompting.
  1. Step through a generic reactor plant startup procedure outline (pre-criticality to rated power) in teams of two, with one student acting as operator and one as verifier; each step is read, performed on the model board or simulator interface, and checked off; roles rotate every five steps.
  2. Respond individually to three sequential off-normal alarm cards (e.g., RCS low pressure, high containment pressure, loss of feedwater flow): for each alarm, write the immediate actions, probable causes, and corrective actions in the correct order before checking against the answer key.
  3. Conduct a post-exercise critique as a group: each student identifies one step they performed correctly and one step where they deviated from the procedure, explains the safety significance of the deviation, and states how procedure adherence supports the NRC safety culture policy on following procedures.
Generic reactor startup procedure outline, alarm response cards (three scenarios), model system board or table-top simulator interface, procedure use and adherence policy handout, NEI 09-07 (safety culture) overviewStudents complete all startup procedure steps in correct sequence with no out-of-order actions and respond to all three alarm cards with at least 80% of required actions correctly sequenced; any skipped immediate action is flagged for remediation.
12Integrated System Interactions and Plant Transient Analysis32practiceStudents will analyze a complex plant transient involving simultaneous off-normal conditions in two or more systems, identify the correct priority order of operator actions, and document findings in a written transient analysis report that meets nuclear quality-writing standards.
  1. Work through a two-system transient scenario (e.g., turbine trip coincident with loss of one emergency diesel generator) in a tabletop exercise: students individually map on a blank plant diagram which systems are affected, which actuate automatically, and which require manual operator action, then compare maps with a partner and reconcile differences.
  2. Write a structured transient analysis report (minimum two pages) for the scenario, using a provided template that requires: event description, automatic system responses, required operator actions in priority order, and radiological consequences of correct versus incorrect response; report must follow technical writing standards with no ambiguous pronoun references and all system names spelled out on first use.
  3. Participate in a whole-class debrief where each team presents their priority action list for peer challenge; instructor corrects any technically inaccurate statements in real time and ties each system interaction back to the applicable lesson and credential exam objective.
Two-system transient scenario packet, blank plant diagram, transient analysis report template, technical writing standards checklist, NEI NUCP plant systems exam objective listTransient analysis report scored against a rubric (accuracy of system responses 40%, correct action priority 40%, technical writing quality 20%); pass mark 80% overall with no critical safety actions omitted or inverted.
Assessments
AssessmentTypeWeightPass standardMethod & rubric
Plant Systems Knowledge ExamWritten exam25%80% correct (40 of 50 questions)A 50-question multiple-choice and short-answer examination covering all major plant systems: primary and secondary coolant systems, ECCS, containment, electrical distribution, and auxiliary systems. Questions are written at the NRC Generic Fundamentals Examination (GFES) cognitive level and mapped to the NRC Non-Licensed Operator and Reactor Operator license exam content areas, as well as the NEI NUCP plant systems module learning objectives.
Standard met · Safety · Time · Quality/finish · Documentation
P&ID and System Lineup Skills DemonstrationSkills demonstration45%All safety-critical valve positions correct; overall lineup accuracy 90% or higher; LOTO permit complete and correct with zero energy isolation errorsStudents receive an unfamiliar generic P&ID segment and a written system lineup checklist, then independently verify the lineup by tracing each valve and instrument against the checklist, documenting discrepancies, and completing a lockout/tagout permit for one isolated component. The evaluator observes the entire exercise and scores using a standardized checklist; any missed energy isolation point results in an automatic fail and mandatory remediation before reassessment.
Standard met · Safety · Time · Quality/finish · Documentation
Lab Log: System Tracing and Transient Analysis PortfolioLog15%All six required entries present and complete; average technical accuracy score of 80% across all entries; no entries with critical safety errorsStudents maintain a cumulative lab log throughout the course containing six required entries: (1) PWR RCS flow path annotation, (2) BWR primary system comparison, (3) secondary system flow diagram, (4) ECCS actuation logic chart, (5) CCW/ESW heat rejection chain map, and (6) the two-system transient analysis report. Each entry is reviewed by the instructor at the time of completion for immediate corrective feedback; the complete portfolio is evaluated at course end for accuracy, completeness, and technical writing quality.
Standard met · Safety · Time · Quality/finish · Documentation
Safety and Procedure Compliance CheckSafety audit15%100% compliance on all safety-critical steps; no LOTO errors; PPE donned correctly before any simulated equipment contact; procedure use score 90% or higherAn unannounced or end-of-course evaluator observation during one of the system evolution practice sessions in which students must demonstrate correct PPE selection and donning, proper use of procedures (no skipped steps, no steps performed from memory without procedure in hand), and complete compliance with lockout/tagout requirements per OSHA 29 CFR 1910.147. Any critical safety deviation (skipped LOTO step, incorrect PPE for the hazard, out-of-sequence safety action) constitutes a failure and requires remediation and re-evaluation before the student may proceed to the next course.
Standard met · Safety · Time · Quality/finish · Documentation
BLD-NUCL84-04 Trade course

Instrumentation & Control for Nuclear Power Plant Operations

313 hr · $6,480 COMPLIMENTARY

This course develops the knowledge and hands-on skills required to install, calibrate, troubleshoot, and maintain the instrumentation and control (I&C) systems found in commercial nuclear power plants. Students work with pressure, temperature, flow, and neutron-flux sensors; analog and digital control loops; and plant protection system logic in accordance with applicable industry standards and NRC requirements. Lessons align with the NEI NUCP Uniform Curriculum I&C competency areas and support preparation for the NRC Non-Licensed Operator and Reactor Operator license examinations.

Outcomes
Course text

This course develops the knowledge and hands-on skills required to install, calibrate, troubleshoot, and maintain the instrumentation and control (I&C) systems found in commercial nuclear power plants. Students work with pressure, temperature, flow, and neutron-flux sensors; analog and digital control loops; and plant protection system logic in accordance with applicable industry standards and NRC requirements. Lessons align with the NEI NUCP Uniform Curriculum I&C competency areas and support preparation for the NRC Non-Licensed Operator and Reactor Operator license examinations.

How the course runs. 12 blocks: I&C Fundamentals: Signals, Standards, and Documentation; Measurement Principles: Pressure, Differential Pressure, and Level; Temperature and Flow Measurement; Neutron Flux Instrumentation and Reactor Power Measurement; Analog Control Loops: PID Controllers and Final Control Elements; Digital I&C Systems and Programmable Logic in Nuclear Applications; Reactor Protection System and Engineered Safety Feature Actuation Logic; Lockout/Tagout and I&C Work Clearance Procedures; Instrument Calibration: Procedure, Data Recording, and As-Found/As-Left Documentation; Troubleshooting I&C Loops: Fault Isolation and Corrective Maintenance; Instrument Surveillance Testing and Technical Specification Compliance; Integrated I&C System Review and Credential Exam Alignment.

What competent looks like. Calibrate and functionally test nuclear-grade process instruments—pressure, differential-pressure, temperature, flow, and level transmitters—to within manufacturer and technical specification tolerances. Trace and interpret I&C loop diagrams, instrument index sheets, and P&IDs using ISA symbology and plant documentation standards. Analyze analog and digital control loop behavior, identify common failure modes, and recommend corrective actions consistent with plant procedures. Describe the design bases, channel independence requirements, and operability testing of a nuclear plant protection system and its engineered safety feature actuation logic. Apply OSHA lockout/tagout, nuclear I&C work clearance, and electrostatic-discharge precautions when performing instrument maintenance tasks. Produce complete calibration data sheets and corrective-maintenance work orders that meet the documentation requirements of 10 CFR Part 50 Appendix B quality assurance.

Lessons · 12 blocks
#LessonHrTypeObjectiveActivitiesMaterialsCheck
1I&C Fundamentals: Signals, Standards, and Documentation19theoryStudents will correctly interpret ISA 5.1 instrument symbols, identify the four standard analog signal ranges used in nuclear plant I&C loops, and locate required information on an instrument data sheet.
  1. Read and annotate a simplified nuclear plant P&ID segment using ISA 5.1 symbol sheets; identify each instrument tag and state its function in writing.
  2. Compare milliamp and voltage signal ranges on sample calibration datasheets; calculate expected output for a given process input using the linear scaling formula.
  3. Complete a guided worksheet matching 20 common ISA tag identifiers (PT, TT, FT, LT, AT, etc.) to their process variable and loop function, then peer-review for accuracy.
ISA 5.1 standard (current edition), sample nuclear plant P&IDs, instrument data sheets, scientific calculators, whiteboardWritten quiz: 80% or higher on 25 questions covering ISA symbology, signal ranges, and datasheet interpretation; instructor reviews each student's annotated P&ID for correct tag identification.
2Measurement Principles: Pressure, Differential Pressure, and Level26.5theoryStudents will explain the operating principles of Bourdon-tube, bellows, and capacitance-cell pressure transmitters and calculate reactor coolant system level from differential-pressure measurements.
  1. Disassemble and reassemble a training-grade DP transmitter, labeling each internal component and its function on a provided diagram.
  2. Solve a set of 10 level-from-DP calculation problems using reference leg and variable leg pressure relationships typical of a pressurized-water reactor steam generator.
  3. Watch an instructor-led demonstration of zero and span checks on a bench-mounted pressure transmitter; record expected versus actual output at five calibration points.
Training-grade capacitance-cell DP transmitter, calibration bench, dead-weight tester or precision pressure calibrator, manufacturer manual, engineering paperPractical check: student correctly identifies all major transmitter components (100% required for safety-critical parts) and solves at least 8 of 10 DP-level calculation problems correctly before advancing.
3Temperature and Flow Measurement24.5theoryStudents will describe the operating principles of RTDs, thermocouples, and orifice-plate flow elements and explain how each is applied in nuclear plant primary and secondary coolant circuits.
  1. Compare RTD resistance-temperature tables with thermocouple millivolt-temperature tables; calculate expected transmitter output for three given process temperatures using each sensor type.
  2. Trace a feedwater flow measurement loop on a plant P&ID from the orifice plate through the DP transmitter to the flow controller; label signal types at each junction.
  3. Participate in a guided discussion on why nuclear plants use redundant RTD channels for overtemperature protection and how channel separation rules apply.
RTD reference tables (IEC 60751 or ASTM equivalent), thermocouple reference tables, sample P&IDs, orifice-plate cutaway model or diagram, whiteboardWritten quiz: 80% or higher on 20 questions covering sensor principles, signal conversion calculations, and loop tracing; instructor spot-checks two calculation problems per student.
4Neutron Flux Instrumentation and Reactor Power Measurement26.5theoryStudents will identify the three nuclear power ranges monitored by in-core and ex-core neutron detectors and explain how flux signals feed into reactor trip and power-level control functions.
  1. Map the source range, intermediate range, and power range detector coverage on a simplified reactor startup curve; annotate the trip setpoints for each range.
  2. Review a reactor protection system functional diagram and trace how a high-flux signal in the power range initiates a reactor trip through the logic circuitry.
  3. Analyze a case study of a startup event involving a neutron flux instrument anomaly; identify the failure mode and the procedural response required by the operating procedure.
Plant-generic neutron flux instrumentation training manual, reactor trip logic diagram, startup curve chart, case study handout (NRC-published generic communication or training scenario)Oral questioning by instructor: student correctly explains detector range overlap and trip logic path with no major errors; written summary of the case study must identify the correct failure mode and response.
5Analog Control Loops: PID Controllers and Final Control Elements26.5demoStudents will configure proportional-integral-derivative (PID) controller parameters on a training process loop simulator and observe the effect of each parameter on loop stability and setpoint response.
  1. Using a PC-based or bench-top process loop trainer, set baseline P, I, and D values for a simulated pressurizer pressure control loop; record step-response curves for each configuration.
  2. Introduce a process disturbance (step load change) and document how adjusting integral time corrects steady-state offset; compare results in a group debrief.
  3. Identify and demonstrate the correct procedure for transferring a controller from automatic to manual and back to automatic, following a simulated plant procedure.
PC-based or bench-top PID process loop trainer (e.g., Feedback Instruments or equivalent), student procedure sheets, graph paper or data-logging software, sample plant operating procedure for controller transferSkills demonstration: student correctly transfers controller to manual and back to auto without process excursion (pass/fail per procedure checklist) and achieves stable setpoint response within ±5% of target after PID adjustment.
6Digital I&C Systems and Programmable Logic in Nuclear Applications24.5theoryStudents will describe the architecture of a typical nuclear digital I&C platform, explain the role of software quality assurance under 10 CFR Part 50 Appendix B, and identify common cybersecurity boundary requirements.
  1. Review a simplified block diagram of a digital reactor protection system; identify the processor, voting logic, communication buses, and isolation devices, and explain each component's function.
  2. Read an excerpt from a digital I&C software test report and identify the test types (unit, integration, factory acceptance, site acceptance) and their acceptance criteria.
  3. Participate in a structured group discussion on why physical and logical isolation of safety-system networks from non-safety networks is required by NRC guidance, citing the general regulatory basis.
Generic digital I&C platform training guide (Westinghouse Common Q or AREVA Teleperm reference material as available), 10 CFR Part 50 Appendix B summary, NRC Regulatory Guide 1.152 overview handout, whiteboardWritten quiz: 80% or higher on 20 questions covering digital I&C architecture, software QA tiers, voting logic, and isolation requirements.
7Reactor Protection System and Engineered Safety Feature Actuation Logic26.5theoryStudents will explain the design bases for a nuclear plant protection system, describe the two-out-of-four voting logic common in pressurized-water reactors, and trace an engineered safety feature actuation signal from initiating sensor to final actuator.
  1. Work through a logic diagram exercise tracing a high reactor coolant system pressure trip signal through a 2-of-4 coincidence circuit to a reactor trip breaker, documenting each step.
  2. Analyze the design basis for channel separation (physical, electrical, and functional independence) using an NRC training reference; list four specific separation requirements in writing.
  3. Role-play a channel operability test walkthrough: one student reads the surveillance procedure step while a partner marks off acceptance criteria on a simulated channel-check data sheet.
Generic RPS logic diagram, 2-of-4 coincidence logic training worksheet, sample nuclear surveillance procedure (de-identified plant document or NRC training material), NRC NUREG training guides as applicableWritten quiz: 80% or higher on 25 questions covering trip logic, channel independence, and ESFAS actuation paths; logic-trace exercise graded for correct signal path with no missed nodes.
8Lockout/Tagout and I&C Work Clearance Procedures19labStudents will correctly execute a nuclear plant I&C work clearance and OSHA-compliant lockout/tagout sequence on a training board, isolating a simulated instrument loop before performing maintenance.
  1. Complete OSHA 10 LOTO module review; identify the six steps of an OSHA-compliant LOTO sequence and apply them to a written scenario involving a 4–20 mA instrument loop.
  2. On a training instrument panel, perform a full clearance: notify the simulated operator, apply tags and locks to isolation valves and electrical disconnects, verify zero energy, and document each step on the clearance form.
  3. Restore the instrument loop to service following the clearance release procedure; verify correct output signal before declaring the instrument operable.
Training instrument panel with lockable isolation valves and electrical disconnects, LOTO locks and tags, clearance form templates, OSHA 29 CFR 1910.147 reference card, multimeterSkills checklist (pass/fail): all six LOTO steps completed in correct order with zero safety steps skipped; clearance form complete and legible; instructor must observe the student independently; any skipped safety step is an automatic retest.
9Instrument Calibration: Procedure, Data Recording, and As-Found/As-Left Documentation30labStudents will perform a five-point calibration on a pressure transmitter following a written procedure, record as-found and as-left data, and determine whether the instrument passes its technical specification tolerance.
  1. Set up a calibration bench: connect a precision pressure source, a reference standard, and a multimeter to a training-grade pressure transmitter; verify all connections before applying pressure.
  2. Apply pressure at 0%, 25%, 50%, 75%, and 100% of calibrated span; record as-found output at each point, calculate error in percent of span, and compare to the acceptance tolerance stated in the procedure.
  3. Adjust zero and span as needed; repeat the five-point check; record as-left data on the official calibration data sheet and sign the completed document.
Training-grade 4–20 mA pressure transmitter, precision pressure calibrator or deadweight tester, NIST-traceable reference standard, digital multimeter, calibration data sheet forms, procedure sheet, Fluke or equivalent calibratorCalibration data sheet reviewed by instructor: as-left errors must be within the stated tolerance at all five calibration points; data sheet must be complete, legible, and signed; any out-of-tolerance as-left result requires rework and re-check.
10Troubleshooting I&C Loops: Fault Isolation and Corrective Maintenance30practiceStudents will systematically isolate an instructor-introduced fault in a complete 4–20 mA instrument loop using a half-split troubleshooting method and document the corrective maintenance action taken.
  1. Given a loop drawing and a symptom (e.g., controller reads full-scale with process at setpoint), develop a fault hypothesis and list three test points to check in half-split sequence before touching the equipment.
  2. Using a multimeter and loop calibrator, check signal levels at each test point; identify the faulted component (sensor, transmitter, cable, or controller input card) and confirm by substitution or isolation.
  3. Complete a corrective maintenance work order: describe the symptom, the diagnostic steps taken, the root cause, the corrective action, and the post-repair operability verification, following a plant work-order template.
Training instrument loop panels with instructor-introduced faults (open wire, shorted sensor, failed transmitter, misconfigured controller), multimeter, 4–20 mA loop calibrator, loop drawings, corrective maintenance work-order formsInstructor observation: student correctly identifies the faulted component within the allotted time using documented half-split logic (no random part swapping allowed); completed work order must describe all required fields; pass requires correct fault isolation and complete documentation.
11Instrument Surveillance Testing and Technical Specification Compliance28fieldStudents will perform a simulated instrument channel operability check following a surveillance test procedure, evaluate results against technical specification acceptance criteria, and determine the required action if a channel fails.
  1. Walk through a sample channel check procedure step-by-step on the lab training panel, verifying that the instrument reading is consistent with the independent indication and plant conditions; record results on the surveillance data sheet.
  2. Introduce a deliberate out-of-tolerance condition; evaluate whether the condition represents a failed channel and, using the technical specification action level framework, determine whether a notification or plant action is required.
  3. Debrief as a class: discuss the difference between a channel check, channel calibration, and channel functional test, and explain the surveillance frequency basis for each.
Lab training panel configured as a safety-related channel, sample surveillance test procedure (de-identified or generic), technical specification action level reference sheet, surveillance data sheet formsCompleted surveillance data sheet reviewed by instructor: all steps performed in order, results recorded correctly, correct determination of pass or fail, and correct action level identified; 100% of safety-critical decision points must be correct.
12Integrated I&C System Review and Credential Exam Alignment32practiceStudents will integrate knowledge from all prior lessons by solving multi-system I&C scenarios drawn from NRC RO license exam question formats and NUCP competency areas, demonstrating readiness for credentialing.
  1. Complete a timed set of 40 practice questions in NRC RO written-exam style covering instrument calibration, protection system logic, control loop behavior, and technical specification application; self-score and review incorrect items.
  2. Work in pairs to trace an end-to-end scenario: a feedwater flow transmitter fails high during plant operation; partners jointly diagnose the I&C response, identify which protection system channels actuate, and state the operator actions per procedure.
  3. Each student prepares a one-page I&C system summary for one assigned plant system (pressurizer, steam generator, reactor coolant pump) describing the key instruments, their setpoints, and their protection system connections, then presents it to the class for peer feedback.
NRC-style practice question bank (instructor-developed or commercial RO exam prep resource), plant system I&C diagrams used throughout the course, presentation materials, scoring rubricPractice exam scored at 80% or higher; one-page system summary graded against rubric for technical accuracy, correct setpoint identification, and clear explanation of protection system connections—must meet all rubric criteria to pass.
Assessments
AssessmentTypeWeightPass standardMethod & rubric
I&C Systems Written ExaminationWritten exam25%80% or higher (40 of 50 questions correct)A 50-question closed-book written exam covering ISA symbology, measurement principles (pressure, temperature, flow, level, neutron flux), analog and digital control loop theory, reactor protection system logic, and technical specification application. Questions are written in NRC RO license exam format to provide authentic credentialing practice aligned with both the NRC Non-Licensed Operator Prep and RO License exam areas.
Standard met · Safety · Time · Quality/finish · Documentation
Instrument Calibration Skills DemonstrationSkills demonstration45%All as-left calibration points within stated tolerance; data sheet complete and signed; all procedural steps completed in correct order without instructor promptingThe student independently performs a five-point calibration on an assigned training-grade transmitter using the course calibration procedure, records as-found and as-left data, and determines instrument acceptability against the technical specification tolerance. The evaluator uses a standardized skill checklist; any missed safety step or out-of-tolerance as-left result requires a documented retest before the student may progress.
Standard met · Safety · Time · Quality/finish · Documentation
Calibration and Maintenance Laboratory LogLog15%All required entries present; technical accuracy verified by instructor; no falsified or blank data fields; submitted within one class day of each lab completionStudents maintain a cumulative lab log throughout the course documenting every calibration exercise, fault-isolation activity, and surveillance test, including as-found data, calculations, results, corrective actions, and post-work verifications. The log is evaluated as a quality assurance record consistent with 10 CFR Part 50 Appendix B documentation standards and serves as evidence of the NUCP I&C practical competency requirements.
Standard met · Safety · Time · Quality/finish · Documentation
Lockout/Tagout and Work Clearance Safety CheckSafety audit15%Pass/fail: all six LOTO steps completed in correct sequence with zero safety steps omitted; any skipped safety-critical step is an automatic failure requiring full retestThe instructor observes the student independently executing a complete OSHA-compliant lockout/tagout and nuclear I&C work clearance sequence on the training panel, from notifying the operator through verification of zero energy state and restoration to service. This assessment maps directly to OSHA 10 hazardous energy control competencies and to the NRC Non-Licensed Operator task area for safe instrument maintenance.
Standard met · Safety · Time · Quality/finish · Documentation
BLD-NUCL84-05 Trade course

Radiation Protection & Dosimetry

313 hr · $6,480 COMPLIMENTARY

This course develops the knowledge and hands-on skills required to monitor, quantify, and control ionizing radiation hazards in a nuclear power plant environment. Students learn the physics of radiation, biological effects, detection instrument operation, dose calculation, and the regulatory framework governing worker radiation protection. Lessons are mapped to the NRRPT examination content areas, the NEI NUCP Uniform Curriculum radiation protection modules, and the NRC Non-Licensed Operator and Reactor Operator license preparation objectives.

Outcomes
Course text

This course develops the knowledge and hands-on skills required to monitor, quantify, and control ionizing radiation hazards in a nuclear power plant environment. Students learn the physics of radiation, biological effects, detection instrument operation, dose calculation, and the regulatory framework governing worker radiation protection. Lessons are mapped to the NRRPT examination content areas, the NEI NUCP Uniform Curriculum radiation protection modules, and the NRC Non-Licensed Operator and Reactor Operator license preparation objectives.

How the course runs. 12 blocks: Atomic Structure, Radioactive Decay, and Radiation Types; Biological Effects of Ionizing Radiation; Dose Quantities, Units, and 10 CFR Part 20 Limits; ALARA Principle and Radiological Work Planning; Radiation Detection Principles and Instrument Types; Radiation Detection Instrument Operation and Field Calibration; Radiological Surveys: Techniques and Documentation; Personnel Dosimetry: TLDs, OSLs, and Electronic Dosimeters; Contamination Control: Entry, Exit, and Decontamination Procedures; Airborne Radioactivity: Sampling, Action Levels, and Respiratory Protection; Dose Records, Reporting, and Radiological Event Response; Integrated Radiation Protection Practical Examination.

What competent looks like. Identify the types of ionizing radiation, their properties, and the appropriate shielding and PPE for each hazard encountered in a nuclear power plant. Operate and calibrate common radiation detection instruments—including Geiger-Müller detectors, ionization chambers, and proportional counters—and interpret their readings accurately. Apply the ALARA principle and time-distance-shielding controls to plan work in radiologically controlled areas and document dose in accordance with 10 CFR Part 20 requirements. Calculate absorbed dose, dose equivalent, effective dose equivalent, and annual dose limits using standard dosimetry equations and conversion factors. Perform radiological surveys, set up contamination controls, and execute proper entry and exit procedures for high-radiation and contamination areas. Interpret personnel dosimetry data, recognize dose trends that require supervisory action, and communicate radiological conditions using correct NRC/ANSI terminology.

Lessons · 12 blocks
#LessonHrTypeObjectiveActivitiesMaterialsCheck
1Atomic Structure, Radioactive Decay, and Radiation Types24theoryStudents will identify the four major types of ionizing radiation, describe their decay mechanisms, and state the penetrating power and shielding requirements of each.
  1. Lecture and annotated diagram exercise: students label alpha, beta, gamma, and neutron radiation on decay-chain charts for common plant nuclides (Co-60, Cs-137, I-131) and write one shielding recommendation for each.
  2. Card-sort activity: students match decay type to detector type, shielding material, and typical source in a nuclear plant, then justify choices in a paired discussion.
  3. Short-answer quiz on half-life calculations using the decay equation A = A₀e^(−λt), requiring at least five worked problems with units checked.
Nuclide chart (Knolls Atomic Power Laboratory edition), whiteboard, scientific calculators, NRC Regulatory Guide 8.29 (Instruction Concerning Risks from Occupational Radiation Exposure), Chart of the NuclidesWritten 20-question quiz on radiation types, decay equations, and shielding; passing score 70% or higher.
2Biological Effects of Ionizing Radiation22theoryStudents will explain stochastic and deterministic effects of radiation exposure and correlate dose quantities (absorbed dose, dose equivalent, effective dose equivalent) with human health risk.
  1. Reading and annotation of ICRP and NRC biological effects summaries; students create a two-column comparison of stochastic versus deterministic effects with dose thresholds noted where established.
  2. Case-study discussion: instructor presents historical occupational exposure scenarios; students identify which effect category applies and what protective action should have been taken.
  3. Dose-unit conversion worksheet: students convert between rad, rem, gray, and sievert for five realistic exposure scenarios, showing each step, then peer-check results.
ICRP Publication 103 excerpts, NRC NUREG/CR-6459 selected chapters, dose-unit conversion reference sheet, calculatorConcept-map assessment where students connect dose quantity to biological endpoint and regulatory limit; instructor evaluates for accuracy of all connections; 70% of connections must be correct to pass.
3Dose Quantities, Units, and 10 CFR Part 20 Limits26theoryStudents will state the occupational and public dose limits from 10 CFR Part 20 and correctly apply dose quantity definitions to calculate whether a worker's dose is within regulatory limits.
  1. Regulatory scavenger hunt: students use 10 CFR Part 20 to locate and record the annual occupational whole-body dose limit, lens-of-eye limit, extremity limit, and dose limit for declared pregnant workers, then present findings to the class.
  2. Dose calculation drill: students receive five worker dosimetry scenarios and must determine whether each worker's cumulative dose is within limits, state which regulatory subpart applies, and recommend the next action if a limit is approached.
  3. Role-play: one student acts as radiation protection technician advising a simulated worker approaching their quarterly dose limit; class evaluates whether communication was technically accurate and professionally appropriate.
10 CFR Part 20 (current edition, printed or online), NRC Regulatory Guide 8.13, dose-limit reference card, calculatorWritten scenario exam: five multi-part dose-limit problems; students must correctly identify the applicable limit, perform the calculation, and state the required action; 70% overall score required to pass.
4ALARA Principle and Radiological Work Planning26theoryStudents will apply the ALARA principle by using time, distance, and shielding controls to develop a written radiological work plan that reduces projected dose to a level as low as reasonably achievable.
  1. ALARA calculation exercise: given a fixed dose rate field, students calculate the dose received at three different distances using the inverse-square law and for three different work durations, then tabulate results and select the lowest-dose combination.
  2. Group radiological work plan (RWP) drafting: teams of three receive a plant maintenance scenario (e.g., valve replacement in a radiologically controlled area) and draft an RWP that specifies PPE, dosimetry, stay time, shielding, and emergency procedures.
  3. Peer-review round: teams exchange RWPs and use a provided checklist to identify any missing ALARA elements; reviewer comments are discussed in whole-class debrief.
Sample plant RWP forms, NRC Regulatory Guide 8.8 (Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations Will Be ALARA), inverse-square-law reference, calculatorInstructor scores the team RWP against a 15-point rubric covering ALARA controls, PPE selection, stay-time calculation, emergency procedures, and documentation completeness; 11 of 15 points required to pass.
5Radiation Detection Principles and Instrument Types28theoryStudents will explain the operating principles of gas-filled detectors (ionization chamber, proportional counter, Geiger-Müller), scintillation detectors, and electronic dosimeters, and select the correct instrument for a given radiation type and measurement range.
  1. Diagram and labeling exercise: students draw and label the voltage-response curve for gas-filled detectors, marking the ionization, proportional, and Geiger-Müller regions and explaining what happens to pulse output in each region.
  2. Instrument-selection decision matrix: students receive eight plant measurement scenarios (gamma survey, neutron survey, alpha contamination check, beta surface contamination, airborne activity sampling, whole-body dose tracking) and select the correct instrument for each with written justification.
  3. Video analysis: students watch a demonstration of a scintillation detector and an ion chamber in use; they document observed operational steps and write one question per instrument about a step they do not yet understand, which are answered in class discussion.
Detector reference charts, Knoll Radiation Detection and Measurement (4th ed.) selected chapters, instrument manufacturer specification sheets (ion chamber, GM survey meter, scintillation probe), projectorWritten 25-question matching and short-answer quiz on detector principles and instrument selection; 70% passing score.
6Radiation Detection Instrument Operation and Field Calibration30labStudents will perform a source check, operability check, and field calibration verification on a GM survey meter and an ionization chamber survey meter following written procedures, and correctly document results.
  1. Procedure walk-through: instructor demonstrates the pre-use check sequence on a GM meter (battery check, response check with a check source, zero check, selector switch function check); students follow along with their own instrument and mark each step complete on a procedure card.
  2. Paired lab: each student pair performs a complete operability and source-check sequence independently on both a GM meter and an ion chamber, records readings, and compares to the instrument's calibration sticker values to determine whether the instrument is within acceptable response range.
  3. Documentation drill: students complete a simulated calibration log entry for both instruments, including date, instrument serial number, check-source identity and activity, observed response, and accept/reject determination; instructor reviews for completeness.
Calibrated GM survey meters (class set), calibrated ion chamber survey meters, certified check sources (low-activity, licensed), instrument calibration record forms, written operability-check procedures, PPE (lab coat, safety glasses)Instructor observes each student completing the full operability check sequence independently; student must complete all steps in correct order, record readings within ±10% of expected check-source response, and produce a complete log entry; all three criteria must be met to pass.
7Radiological Surveys: Techniques and Documentation28practiceStudents will conduct a systematic area radiation survey and a surface contamination survey in a simulated radiological work area using correct scan speeds, geometries, and instrument settings, and produce a completed survey map.
  1. Instructor demonstration in the training lab: the instructor performs a step-by-step area radiation survey of a mock RCA mockup, narrating instrument settings, scan speed, and distance from surface; students take observation notes and ask clarifying questions.
  2. Student survey exercise: each student conducts an independent area survey of a pre-set mock contaminated area (using approved sealed demonstration sources) while an instructor observer checks scan speed, probe-to-surface distance, and systematic coverage pattern.
  3. Survey map completion: students transfer their readings to a blank plant-area diagram, mark locations and dose rates, identify the highest-dose location, post a simulated radiological posting sign at the correct boundary, and submit the map for review.
GM meters with thin-window probes, ion chamber meters, approved sealed demonstration sources or simulated contamination materials per RSO authorization, area-survey map templates, radiological posting signs, PPE (lab coat, safety glasses, gloves), written survey procedureInstructor uses a 12-point observation checklist (correct probe distance, adequate scan speed, systematic coverage, correct instrument setting, accurate map transfer, correct posting placement); students must achieve 10 of 12 points to pass.
8Personnel Dosimetry: TLDs, OSLs, and Electronic Dosimeters24theoryStudents will describe the operating principles of thermoluminescent dosimeters, optically stimulated luminescence dosimeters, and electronic personal dosimeters, and correctly assign, wear, and exchange dosimetry according to plant access control procedures.
  1. Dosimeter teardown and anatomy review: instructor shows cross-section diagrams and, where available, sample non-activated TLD/OSL badge components; students label components and write a brief explanation of how energy is stored and read.
  2. Scenario-based dosimeter assignment drill: students receive five worker profiles (whole-body worker, extremity work, declared pregnant worker, visitor, high-radiation area worker) and select the correct dosimeter type(s) and wearing location for each, citing the applicable regulatory or plant-procedure basis.
  3. Electronic dosimeter (EPD) reading exercise: using training EPDs or simulators, students enter a simulated RCA, note the preset alarm setpoint, read the accumulated dose display at intervals, and record entries and exits in a simulated access-control log.
Sample TLD and OSL badge assemblies (non-activated or training units), electronic personal dosimeters or training simulators, 10 CFR Part 20 subpart C reference, sample plant access-control procedure, dosimetry assignment log formsWritten 15-question quiz on dosimeter principles, wearing requirements, and regulatory basis for assignment decisions; 70% passing score required.
9Contamination Control: Entry, Exit, and Decontamination Procedures28practiceStudents will demonstrate correct step-off pad procedure, anti-contamination clothing donning and doffing sequence, and basic personnel decontamination technique while maintaining their own skin and clothing free of detectable contamination.
  1. Instructor demonstration of full anti-C donning sequence (coveralls, boot covers, inner and outer gloves, hood, respirator as required) and doffing sequence at a step-off pad, with explicit instruction on the roll-away technique to contain contamination; students observe and annotate a procedure checklist.
  2. Paired donning/doffing drill: student pairs take turns donning full anti-C clothing and doffing at a step-off pad while the partner observes against the checklist and provides corrective feedback; roles then switch.
  3. Simulated frisk: after doffing, each student performs a self-frisk with a GM meter at a simulated frisker station, scanning hands, feet, and face at the correct probe-to-skin distance and speed; instructor observes and provides correction for missed areas.
Anti-contamination clothing (coveralls, boot covers, gloves, hoods), step-off pad, GM thin-window frisker meters, contamination control procedure, PPE, simulated step-off pad boundary tapeInstructor evaluates each student's independent doffing and self-frisk using an 8-point checklist; all 8 steps must be performed correctly (100% required for this safety-critical skill) or the student repeats with remediation.
10Airborne Radioactivity: Sampling, Action Levels, and Respiratory Protection26demoStudents will set up an air sampling train to measure airborne radioactivity concentration, compare results to derived air concentration values, and select the correct respiratory protection based on the calculated dose potential.
  1. Instructor demonstration of air sampler setup: filter holder assembly, pump connection, flow-rate verification with a calibrated rotameter or electronic flow meter, and sample collection procedure; students follow a written procedure and annotate each step.
  2. DAC calculation exercise: using provided airborne concentration data (activity per unit volume), students calculate the fraction of the applicable DAC from 10 CFR Part 20 Appendix B and determine whether respiratory protection is required, documenting their work.
  3. Respirator selection and fit-check practice: students review the plant respiratory protection program tiers (filtering face piece, half-face, full-face, supplied air) and, given three airborne hazard scenarios with specified DAC fractions, select the correct respirator class and perform a positive/negative pressure user seal check on a training half-face respirator.
Air sampling pump and filter holder assembly, calibrated flow meter, 10 CFR Part 20 Appendix B DAC tables, training half-face respirators, written airborne sampling procedure, calculator, PPEStudents submit completed DAC calculation worksheet for three scenarios (must be arithmetically correct and include the correct action recommendation) and demonstrate the seal check; both components must be satisfactory to pass.
11Dose Records, Reporting, and Radiological Event Response26theoryStudents will interpret a worker dose record, identify when regulatory reporting thresholds under 10 CFR Part 20 are met or approached, and describe the immediate actions required upon a radiological event such as an inadvertent high-radiation area entry.
  1. Dose record analysis: students receive five simulated worker dose history printouts showing quarterly and annual accumulated doses; they identify which workers have reached or exceeded investigation levels, which have exceeded regulatory limits, and what actions are required for each.
  2. Regulatory reporting research: using 10 CFR Part 20 Subparts L and M, students identify the reporting requirements (who is notified, within what timeframe) for overexposures and incidents, and summarize findings in a one-page table.
  3. Emergency response scenario: instructor describes an inadvertent entry into a high-radiation area; students write the sequence of immediate protective actions the worker and HP technician must take, including notification, dose assessment, and event documentation steps.
10 CFR Part 20 Subparts L and M (printed excerpt), simulated worker dose history printouts, reporting timeline reference chart, scenario handoutShort-answer written assessment on dose record interpretation and reporting requirements; students must correctly identify all reportable conditions in the five records and list correct notification actions; 70% score required to pass.
12Integrated Radiation Protection Practical Examination25labStudents will independently complete a full radiological work scenario—from pre-job briefing through survey, anti-C donning, simulated task execution, frisk, doffing, and documentation—demonstrating all major course competencies without prompting.
  1. Pre-job briefing: each student reviews a written RWP for a simulated maintenance task in a mock RCA, verifies dose limits and stay time, selects correct dosimetry and PPE, and delivers a one-minute verbal pre-job safety brief to the instructor.
  2. Integrated practical: student performs an area radiation survey of the mock RCA, dons anti-C clothing, enters the area with dosimeter, completes a simulated task (e.g., connecting a hose fitting), monitors dose accumulation on EPD, exits when stay time is reached, and doffs at the step-off pad with self-frisk.
  3. Post-job documentation: student completes a survey map, dosimetry log entry, and a brief written post-job ALARA critique identifying one change that would have further reduced dose.
Full mock RCA setup with boundary tape, radiological postings, sealed demonstration sources or simulated contamination per RSO authorization, anti-C clothing, GM meters, ion chambers, EPDs, step-off pad, RWP forms, survey map templates, dosimetry logInstructor scores each student on a 20-point integrated performance rubric covering pre-job brief accuracy (4 pts), survey technique (4 pts), anti-C donning/doffing (4 pts), dosimetry monitoring (4 pts), and documentation completeness (4 pts); 16 of 20 points required to pass; any safety-critical error (e.g., leaving the RCA without frisking) results in automatic remediation regardless of total score.
Assessments
AssessmentTypeWeightPass standardMethod & rubric
Radiation Protection Written Knowledge ExaminationWritten exam25%70% or higher (105 of 150 points)A 150-question written examination covering radiation physics, biological effects, dose quantities and units, 10 CFR Part 20 limits, ALARA principles, detector theory, dosimetry systems, contamination control, airborne radioactivity, and regulatory reporting. Questions are drawn from NRRPT examination content domains and NEI NUCP radiation protection module objectives, using multiple-choice, matching, and calculation formats.
Standard met · Safety · Time · Quality/finish · Documentation
Instrument Operation and Radiological Survey Skills DemonstrationSkills demonstration45%All safety-critical steps performed correctly; 85% overall on the scored checklistThe student independently performs a GM meter operability check, conducts an area radiation survey and surface contamination survey of a mock RCA, and correctly documents all results. An instructor scores performance on a detailed observation checklist aligned to plant HP technician task qualification standards.
Standard met · Safety · Time · Quality/finish · Documentation
Laboratory Procedure LogLog15%All six required lab entries present, complete, and accurate; no blank data fields; any calculation error corrected and initialedStudents maintain a bound laboratory log throughout the course recording procedures, raw data, calculated results, and conclusions for each of the six laboratory and practice sessions (instrument operability, area survey, contamination survey, dosimeter assignment, air sampling, and integrated practical). The log is reviewed by the instructor for completeness, data integrity, and correct unit usage at the end of the course.
Standard met · Safety · Time · Quality/finish · Documentation
Radiological Safety Behavior Observation ChecklistSafety audit15%100% compliance on all eight non-negotiable safety behaviors; any single failure requires documented remediation and re-observationThe instructor conducts a final safety-behavior observation during the integrated practical lesson, verifying eight non-negotiable behaviors: correct dosimeter worn before entering RCA, stay time respected, self-frisk completed at step-off pad, anti-C doffing performed with roll-away technique, no eating or drinking in the RCA, correct PPE selected for hazard, RWP reviewed before entry, and emergency exit route identified at pre-job brief.
Standard met · Safety · Time · Quality/finish · Documentation
BLD-NUCL84-06 Trade course

NRC Regulations & Safety Culture

313 hr · $6,480 COMPLIMENTARY

This course develops the regulatory knowledge and professional safety-culture behaviors required of nuclear plant technicians and operators operating under NRC oversight. Students study the Atomic Energy Act, 10 CFR Parts 19, 20, 50, and 55, the NRC inspection and enforcement process, and the industry safety-culture framework established in NRC Policy Statement and INPO guidelines. Emphasis is placed on applying regulations to realistic plant scenarios, recognizing regulatory violations, and demonstrating the safety-conscious work environment (SCWE) behaviors expected by both the NRC and utility employers.

Outcomes
Course text

This course develops the regulatory knowledge and professional safety-culture behaviors required of nuclear plant technicians and operators operating under NRC oversight. Students study the Atomic Energy Act, 10 CFR Parts 19, 20, 50, and 55, the NRC inspection and enforcement process, and the industry safety-culture framework established in NRC Policy Statement and INPO guidelines. Emphasis is placed on applying regulations to realistic plant scenarios, recognizing regulatory violations, and demonstrating the safety-conscious work environment (SCWE) behaviors expected by both the NRC and utility employers.

How the course runs. 12 blocks: Foundation of Nuclear Law: Atomic Energy Act & NRC Authority; 10 CFR Part 19: Notices, Instructions & Reports to Workers; 10 CFR Part 20: Radiation Protection Standards; 10 CFR Part 50: Domestic Licensing of Production & Utilization Facilities; 10 CFR Part 55: Operator Licensing Requirements; Technical Specifications: LCOs, Required Actions & Surveillance Requirements; NRC Inspection Program & Reactor Oversight Process; NRC Enforcement Policy: Violations, Civil Penalties & Orders; NRC Safety Culture Policy Statement & the Nine Traits; Safety-Conscious Work Environment (SCWE) & Corrective Action Program; Human Performance Tools & Pre-Job Briefs; Integrated Regulatory Compliance Scenarios.

What competent looks like. Correctly interpret and apply the key requirements of 10 CFR Parts 19, 20, 50, and 55 to plant technician and operator duties. Explain the NRC's regulatory framework including the Atomic Energy Act authority, the licensing process, inspection program, and enforcement process including levels of violation. Describe the nine safety-culture traits identified in the NRC Safety Culture Policy Statement and provide plant-scenario examples demonstrating each trait. Identify a nuclear safety-conscious work environment (SCWE) violation and demonstrate the proper adverse-condition reporting pathway including the corrective action program (CAP). Interpret a Technical Specification limiting condition for operation (LCO), its required actions, and its completion times using a sample plant Technical Specifications document. Complete a simulated NRC pre-job brief, post-job review, and condition report accurately and in the format required by plant administrative procedures.

Lessons · 12 blocks
#LessonHrTypeObjectiveActivitiesMaterialsCheck
1Foundation of Nuclear Law: Atomic Energy Act & NRC Authority20theoryStudents will explain how the Atomic Energy Act of 1954, as amended, establishes the NRC's legal authority to regulate civilian nuclear power and will identify the organizational divisions of the NRC that affect plant operations.
  1. Read excerpts from the Atomic Energy Act of 1954 and the Energy Reorganization Act of 1974; annotate key sections that transfer authority from the AEC to the NRC and note implications for plant workers.
  2. Map the NRC's organizational structure (Commission, regional offices, Office of Nuclear Reactor Regulation, Office of Nuclear Material Safety and Safeguards) on a blank org-chart template and match each office to a scenario card describing a plant event.
  3. Group discussion: analyze a case study of a historical NRC enforcement action and identify which statutory authority the NRC invoked; present findings to the class.
Atomic Energy Act of 1954 (public domain text), Energy Reorganization Act of 1974, NRC public website org-chart, regional-office boundary map, scenario cards, whiteboardShort written quiz of 15 multiple-choice questions covering AEA authority, NRC structure, and regional jurisdiction; pass mark 80%.
210 CFR Part 19: Notices, Instructions & Reports to Workers22theoryStudents will accurately describe the rights and responsibilities that 10 CFR Part 19 grants to radiation workers and will draft a compliant worker-notification posting.
  1. Read 10 CFR Part 19 in full; complete a structured-notes worksheet identifying each section's key requirement and to whom it applies (employer vs. worker).
  2. Role-play exercise: one student acts as a new radiation worker requesting a copy of their radiation exposure records under Part 19; a partner acts as the radiation protection supervisor and walks through the proper response procedure step by step.
  3. Draft a model NRC Form 3 posting notice and a simulated site-level worker notification memo; peer-review for completeness against the Part 19 checklist.
10 CFR Part 19 (NRC Electronic Code of Federal Regulations), NRC Form 3 sample, structured-notes worksheet, peer-review checklistInstructor reviews each student's drafted worker-notification memo against a Part 19 compliance rubric; all required elements present and no inaccuracies = pass.
310 CFR Part 20: Radiation Protection Standards30theoryStudents will apply occupational dose limits, ALARAprinciples, and controlled/restricted area requirements from 10 CFR Part 20 to given exposure scenarios and determine compliance.
  1. Work through a set of 10 scenario cards showing hypothetical annual dose records; determine for each whether the worker is within Part 20 occupational limits, note any ALARA concern, and recommend corrective action where warranted.
  2. Compare the Part 20 dose-limit structure (whole-body, extremity, lens of eye, declared pregnant worker) using a structured comparison table; then apply limits to two sample plant dosimetry records.
  3. Classroom debate: given a scenario where a worker's dose is within limits but not ALARA, one group argues a procedural violation has occurred and the other argues it has not; both groups cite Part 20 sections to support their position.
10 CFR Part 20 (current edition), scenario dose-record cards, comparison-table worksheet, sample dosimetry printouts (simulated)Written exam of 20 questions requiring limit calculations and compliance determinations; pass mark 80%.
410 CFR Part 50: Domestic Licensing of Production & Utilization Facilities35theoryStudents will identify the key licensing requirements, technical specifications, quality assurance appendix, and emergency planning requirements contained in 10 CFR Part 50 that directly affect daily plant technician and operator work.
  1. Using a highlighted copy of 10 CFR Part 50, locate and annotate the sections covering: license conditions, Technical Specifications authority, 10 CFR 50.59 change process, Appendix B Quality Assurance criteria, and emergency planning requirements; record findings on a concept map.
  2. Analyze a sample 10 CFR 50.59 screening form for a proposed plant modification; identify whether the change requires prior NRC approval and justify the determination by citing the appropriate criteria.
  3. Small-group exercise: each group is assigned one Appendix B QA criterion and creates a one-page poster explaining its requirement, how it is implemented at a plant, and what happens when it is violated.
10 CFR Part 50 (NRC eCFR), sample 50.59 screening form, Appendix B QA poster template, concept-map templateInstructor-evaluated concept map and 50.59 screening-form analysis; concept map must correctly identify all five targeted sections; 50.59 determination must be correct with supporting citation.
510 CFR Part 55: Operator Licensing Requirements25theoryStudents will describe the NRC operator licensing process under 10 CFR Part 55, including the requirements for initial licensing, requalification, medical fitness, and conditions under which a license may be suspended or revoked.
  1. Trace the lifecycle of an NRC Reactor Operator license from initial application through requalification using a process-flow diagram activity; annotate each step with the applicable Part 55 section.
  2. Review sample NRC operator license conditions and a simulated requalification-cycle record; determine whether the licensee is in compliance with annual and biennial requirements.
  3. Case study discussion: review a publicly available NRC enforcement case involving an operator license condition; identify which Part 55 requirements were violated, what enforcement action was taken, and what corrective actions were ordered.
10 CFR Part 55, sample operator license (NRC public document), requalification-record worksheet, NRC enforcement-case summary (public), process-flow diagram templateOral Q&A with instructor: student must correctly answer 4 of 5 questions on the Part 55 lifecycle, medical requirements, and requalification obligations.
6Technical Specifications: LCOs, Required Actions & Surveillance Requirements30demoStudents will correctly interpret a Limiting Condition for Operation (LCO), identify the applicable required actions and completion times, and determine when a plant must enter or exit an action level, using a sample set of Technical Specifications.
  1. Instructor demonstrates how to navigate the three-column format of a Standard Technical Specification (Background, Technical Specification, Bases) using a sample publicly available STS document; students follow along and flag LCO entry conditions on their own copy.
  2. Students work through five progressively complex TS scenarios (e.g., one train of a required system inoperable, reactor coolant leakage exceeding limit); for each, they identify the LCO, required action, and completion time on a structured worksheet.
  3. Timed exercise simulating shift-turnover: student must read a simulated shift log showing two open action levels, determine which completion times are approaching, and brief the class on required actions within a set time limit.
NRC Standard Technical Specifications (publicly available for reference reactor type), sample shift log, TS scenario worksheet, timerAll five scenario worksheets graded; student must correctly identify the LCO entry condition, required action, and completion time on at least 4 of 5 scenarios to pass.
7NRC Inspection Program & Reactor Oversight Process22theoryStudents will describe how the NRC Reactor Oversight Process (ROP) uses performance indicators and inspection findings to categorize plant performance and will explain what a finding of White, Yellow, or Red significance level means for a plant's operating status.
  1. Study the NRC ROP action matrix using the public NRC guidance document; annotate the strategic performance area columns and the significance-threshold rows; identify where each color-coded finding leads on the matrix.
  2. Using the NRC public website's plant performance dashboard (accessed in class), locate two operating plants' current performance-indicator status; record findings and discuss what regulatory response, if any, is triggered.
  3. Simulation: instructor presents a fictional plant event narrative; students determine whether it would be a Green, White, Yellow, or Red finding using the significance-determination process (SDP) flowchart and defend their answer citing ROP criteria.
NRC Reactor Oversight Process description (public NRC document), ROP action matrix, NRC plant performance dashboard (internet access), SDP flowchart (public NRC document)Written short-answer quiz: 10 questions on ROP structure and significance levels; pass mark 80%.
8NRC Enforcement Policy: Violations, Civil Penalties & Orders20theoryStudents will classify a described regulatory violation into the NRC Enforcement Policy's severity-level scheme and predict the likely enforcement response for licensees and for individuals.
  1. Read the NRC Enforcement Policy (public document); complete a classification table listing the characteristics that distinguish Severity Level I through IV violations and the typical enforcement actions associated with each.
  2. Review three sanitized but real NRC enforcement action letters (available on NRC public website); for each, identify the alleged violation, severity level assigned, and penalty or order imposed; compare with class predictions.
  3. Group role-play: half the group represents an NRC enforcement panel; the other half represents plant management responding to a predecisional enforcement conference for a simulated Severity Level III violation; conduct a 10-minute mock conference and debrief.
NRC Enforcement Policy (public document), three sample NRC enforcement letters (public), violation-classification table worksheetInstructor-evaluated classification table: all four severity levels correctly characterized and enforcement responses accurate = pass.
9NRC Safety Culture Policy Statement & the Nine Traits28theoryStudents will define each of the nine safety-culture traits from the NRC Safety Culture Policy Statement and provide a workplace example demonstrating either a healthy or degraded expression of each trait.
  1. Assign each student two of the nine safety-culture traits; each student reads the Policy Statement description of their traits and prepares a two-minute summary explaining the trait and one positive and one negative plant-behavior example.
  2. Watch and analyze two publicly available NRC safety-culture inspection videos or case summaries (NRC public outreach materials); identify which traits were weak in each case and which regulatory or industry actions were taken.
  3. Whole-class sorting exercise: instructor distributes 18 behavior-description cards (two per trait, one healthy and one degraded); students sort cards into the correct trait bucket and justify each placement by citing the Policy Statement.
NRC Safety Culture Policy Statement (Federal Register, public), NRC safety-culture outreach videos or case summaries (NRC.gov), behavior-description card set, Policy Statement summary handoutStudents must correctly sort at least 16 of 18 behavior cards with accurate justifications; each student's two-minute trait summary must include accurate definition and both examples.
10Safety-Conscious Work Environment (SCWE) & Corrective Action Program30practiceStudents will demonstrate the proper pathway for identifying, documenting, and escalating a nuclear safety concern through the plant corrective action program (CAP) without fear of retaliation, in compliance with 10 CFR 50.7 and NRC guidance.
  1. Students each complete a simulated condition report (CR) form for three provided plant-anomaly scenarios ranging from a minor procedure deficiency to a potential safety-significant equipment problem; instructor reviews CR quality for completeness and threshold correctness.
  2. Role-play a chilling effect scenario: one student plays a worker who observed a safety concern but is reluctant to report it due to peer pressure; a partner demonstrates the proper SCWE response, citing 10 CFR 50.7 employee protection provisions and the CAP process.
  3. Map the complete CAP workflow on a process-flow diagram from initial CR entry through operability determination, root cause evaluation, and corrective action verification; annotate where NRC reporting requirements (e.g., 10 CFR 50.72 and 50.73) are triggered.
Simulated CR forms, 10 CFR 50.7, 10 CFR 50.72 and 50.73 (NRC eCFR), CAP workflow template, scenario cards, INPO ACAD guidance summaryAll three CR forms reviewed by instructor: threshold correctly identified, all required data fields complete, and appropriate escalation path chosen on at least 2 of 3 CRs = pass.
11Human Performance Tools & Pre-Job Briefs30practiceStudents will conduct a structured pre-job brief and a post-job review for a simulated maintenance or operations task using the INPO-recommended human-performance tools and demonstrate error-prevention behaviors throughout.
  1. Instructor demonstrates a complete pre-job brief for a simulated valve lineup procedure, using the standard brief format (task objective, hazards, stop conditions, roles, human-performance tools selected); students evaluate the brief against a checklist.
  2. Student pairs take turns leading and critiquing pre-job briefs for three different simulated tasks (one instrumentation check, one chemistry sample, one equipment clearance); evaluator partner scores using the brief checklist.
  3. Conduct a post-job review for a simulated task that encountered an unexpected condition mid-task; students identify what went differently than planned, what human-performance defenses were used, and what should be entered into the CAP.
Pre-job brief format checklist (INPO ACAD-based), sample procedure cards for three tasks, post-job review template, simulated unexpected-condition scenario cardInstructor observes one live pre-job brief per student and scores against the checklist; student must hit all required content elements with no safety-significant omissions to pass.
12Integrated Regulatory Compliance Scenarios21labStudents will apply 10 CFR Parts 19, 20, 50, and 55, Technical Specifications, and safety-culture principles together to analyze a complex, multi-issue plant scenario and produce a written compliance determination.
  1. Instructor presents a multi-page scenario packet describing a simulated plant event that involves a TS action level, a potential Part 20 dose overexposure, a SCWE concern, and a possible 50.59 screening trigger; students read and annotate independently.
  2. In small groups, students develop a written compliance-determination report identifying each regulatory issue in the scenario, the applicable regulation, and the required plant response; groups must also identify any NRC-reportable conditions.
  3. Groups present their compliance-determination reports to the class; the instructor plays the role of an NRC inspector asking follow-up questions; classmates evaluate each presentation for accuracy using a peer-review scoring sheet.
Multi-issue scenario packet, 10 CFR Parts 19/20/50/55 references, TS sample document, compliance-determination report template, peer-review scoring sheetWritten compliance-determination report graded by instructor: all regulatory issues identified, correct regulation cited, and required plant action accurately described for at least 4 of the 5 embedded issues = pass.
Assessments
AssessmentTypeWeightPass standardMethod & rubric
NRC Regulations Written ExamWritten exam25%80% correct (40 of 50 questions)A 50-question multiple-choice and short-answer exam covering 10 CFR Parts 19, 20, 50, and 55; the NRC Reactor Oversight Process; NRC enforcement policy; and the safety-culture policy statement. Questions are mapped to NRC Non-Licensed Operator and Reactor Operator license exam topic areas so that performance on this assessment predicts readiness for those credential exams.
Standard met · Safety · Time · Quality/finish · Documentation
Pre-Job Brief & Compliance Determination Skills DemonstrationSkills demonstration45%All required pre-job brief content elements present with no safety-significant omissions; compliance-determination report identifies all embedded regulatory issues with correct citationThe student conducts a live pre-job brief for an instructor-selected simulated plant task and then submits a written compliance-determination report for a multi-issue regulatory scenario. The instructor evaluates both products using standardized rubrics aligned to NUCP Uniform Curriculum and NRC inspection expectations.
Standard met · Safety · Time · Quality/finish · Documentation
Condition Report & Regulatory Scenario Lab LogLog15%At least 80% of entries complete and accurate across all submitted CR forms and scenario worksheetsStudents submit a compiled lab log containing all completed condition report forms, TS scenario worksheets, 50.59 screening forms, and the CAP workflow diagram produced during the course. The log is reviewed for accuracy, completeness, and correct regulatory citation, demonstrating the documentation habits expected on the job.
Standard met · Safety · Time · Quality/finish · Documentation
Safety Culture Behavior Safety CheckSafety audit15%No degraded safety-culture behaviors observed during any assessed activity; SCWE and human-performance tool use must be demonstrated correctly in at least three separate observed exercisesThroughout the skills demonstration and lab activities, the instructor uses a safety-culture behavior observation checklist aligned to the nine NRC Policy Statement traits to verify that the student consistently demonstrates a safety-conscious work environment: raising concerns without hesitation, using human-performance tools correctly, completing condition reports accurately, and never bypassing a required stop condition.
Standard met · Safety · Time · Quality/finish · Documentation
BLD-NUCL84-07 Trade course

Simulator Training for Nuclear Plant Operations

313 hr · $6,480 COMPLIMENTARY

Students develop hands-on proficiency in nuclear plant operations through progressive simulator exercises that replicate actual control room environments, normal operating procedures, and emergency response scenarios. Using full-scope and part-task simulators, students practice procedure adherence, team communication, and critical system control under realistic plant conditions. Lesson content directly supports NRC Non-Licensed Operator and Reactor Operator license exam areas, NUCP Uniform Curriculum competencies, and NRRPT scenario-based radiation protection decision-making.

Outcomes
Course text

Students develop hands-on proficiency in nuclear plant operations through progressive simulator exercises that replicate actual control room environments, normal operating procedures, and emergency response scenarios. Using full-scope and part-task simulators, students practice procedure adherence, team communication, and critical system control under realistic plant conditions. Lesson content directly supports NRC Non-Licensed Operator and Reactor Operator license exam areas, NUCP Uniform Curriculum competencies, and NRRPT scenario-based radiation protection decision-making.

How the course runs. 12 blocks: Simulator Familiarization and Control Room Layout; Simulator Operating Procedures and Procedure-Use Standards; Nuclear Safety Culture and Human Performance Tools in the Control Room; Normal Plant Startup Procedures on the Simulator; Power Ascension, Steady-State Operations, and Flux Monitoring; Controlled Shutdown and Cooldown Operations; Abnormal Operating Procedures — Instrument Failures and Off-Normal Conditions; Emergency Operating Procedures — Loss-of-Coolant Accident Response; Station Blackout and Loss-of-Feedwater Emergency Response; Radiation Protection Integration in Simulator Operations; Lockout/Tagout Coordination from the Control Room; Integrated Full-Scope Simulator Practical and Post-Shift Critique.

What competent looks like. Execute normal operating procedures for reactor startup, power ascension, steady-state operation, and controlled shutdown on a nuclear plant simulator with 100% procedural compliance verified by a licensed instructor. Respond to simulated abnormal and emergency operating procedure (AOP/EOP) activations—including loss-of-coolant, loss-of-feedwater, and station blackout scenarios—following approved procedure steps in correct sequence. Apply conservative decision-making and nuclear safety culture principles during simulator exercises, demonstrating adherence to the three-way communication standard and procedure-use requirements. Monitor and control simulated plant parameters—reactor power, coolant temperature, pressure, and flow—within technical specification limits using panel instrumentation and computerized displays. Demonstrate correct lockout/tagout initiation, radiation work permit compliance, and emergency communication protocols during simulator-integrated safety drills. Document post-exercise critiques with specific identification of procedure deviations, human performance errors, and corrective actions in a structured shift-log format.

Lessons · 12 blocks
#LessonHrTypeObjectiveActivitiesMaterialsCheck
1Simulator Familiarization and Control Room Layout20demoStudents identify and locate every major panel, control station, and annunciator grouping in the simulated control room and explain the purpose of each section.
  1. Instructor-led walkdown of the simulator control room panels, with students recording panel designations, associated systems, and key instrumentation on a provided layout map.
  2. Students complete a timed panel-identification quiz at the simulator, pointing to and verbally naming 40 randomly called control room components within a 30-minute period.
  3. Paired exercise in which one student describes a control action verbally and the partner locates and marks the correct control on the panel diagram, then partners switch roles.
Full-scope or representative plant simulator, control room layout drawings, panel identification checklist, simulator operating manual (plant-specific or training replica), pencils and graph paper for mappingStudents correctly identify at least 36 of 40 called components (90%) on the timed panel ID quiz; instructor verifies layout map completion and accuracy.
2Simulator Operating Procedures and Procedure-Use Standards22theoryStudents explain the hierarchy of plant procedures—normal, abnormal, and emergency operating procedures—and demonstrate correct continuous-use procedure technique at the simulator.
  1. Lecture and discussion on procedure hierarchy, revision control, and the NRC-supported expectation that procedures are followed as written; students annotate a sample procedure set to identify step types, cautions, and notes.
  2. Students practice the continuous-use technique by reading each step aloud, performing the action, and verbally verifying the expected response on a non-powered simulator panel while an instructor observes.
  3. Small-group case-study review of two documented industry events in which procedure deviations contributed to plant transients; groups present root-cause findings and corrective procedure-use practices to the class.
Sample normal operating procedures (NOPs) and emergency operating procedures (EOPs) from training manuals, procedure-use standards reference guide (INPO-aligned), event case-study handouts, simulator panels (non-powered review mode)Written 20-question quiz on procedure hierarchy and use standards; passing score 80%; instructor observes at least one continuous-use procedure run and marks a behavioral checklist (all critical steps must be demonstrated correctly).
3Nuclear Safety Culture and Human Performance Tools in the Control Room18theoryStudents apply INPO and NRC safety culture traits—including conservative decision-making, questioning attitude, and three-way communication—during simulated shift activities.
  1. Structured lecture on the NRC's definition of safety culture and INPO's nuclear safety culture and climate model; students complete a self-assessment checklist linking each trait to a specific control room behavior.
  2. Role-play exercise at the simulator in which students practice three-way communication (initiator states, receiver repeats, initiator confirms) on ten simulated control actions while a peer evaluates using a standardized checklist.
  3. Students review three short video vignettes of simulated control room interactions, identify which human performance tools are being used or missed, and write a one-paragraph critique for each vignette.
NRC safety culture policy statement document (public), INPO nuclear safety culture traits reference handout, three-way communication evaluation checklist, video vignettes (training library), student critique worksheetsThree-way communication checklist: 9 of 10 practice actions executed correctly (90%); written quiz on safety culture traits scores at least 80%.
4Normal Plant Startup Procedures on the Simulator30practiceStudents conduct a complete reactor startup from cold shutdown to initial criticality following the plant normal operating procedure, maintaining all parameters within specified limits.
  1. Pre-exercise briefing: students review the applicable NOP startup section, identify hold points, required surveillances, and key parameter limits; instructor walks through the expected sequence on a static panel diagram.
  2. Students rotate through operator roles (reactor operator at the panel, shift supervisor, and independent verifier) during a full cold-startup evolution on the simulator, each student completing at least one complete role.
  3. Post-exercise critique in which the instructor freezes the simulator at key decision points and students explain the technical basis for each major action, then complete a structured shift-log entry for the startup evolution.
Simulator configured for cold-shutdown initial conditions, plant normal startup NOP (training version), parameter limit reference cards, startup checklist, shift-log forms, stopwatch for timing hold pointsInstructor evaluates each student's operator role using a step-by-step performance checklist; all critical steps must be completed in correct sequence with no skipped cautions; post-exercise critique shift-log entry graded pass/fail (pass = all required entries present and accurate).
5Power Ascension, Steady-State Operations, and Flux Monitoring28practiceStudents control reactor power from initial criticality to full-power steady state while monitoring axial flux distribution, coolant parameters, and Technical Specification limits throughout the ascension.
  1. Students practice step-wise power ascension on the simulator in 10% power increments, pausing at each plateau to record neutron flux, reactor coolant system temperature, pressure, and flow in a data table and verify against Technical Specification limits.
  2. Instructor introduces an out-of-limit axial flux condition mid-ascension; students identify the anomaly from instrumentation, take conservative action per procedure, and document the event in the shift log.
  3. Students complete a graphical analysis exercise plotting power, temperature, and flux versus time from their recorded data to identify trends and confirm steady-state conditions were achieved and maintained.
Simulator at post-criticality initial conditions, power ascension NOP, flux monitoring procedure, Technical Specification limit reference sheets, data-recording worksheets, graph paper or spreadsheet access, shift-log formsData table graded for completeness and accuracy (all required parameter recordings present, values within logged ±2% of simulator actual); out-of-limit response checklist: correct identification and conservative action within 2 minutes of annunciator alarm (pass/fail).
6Controlled Shutdown and Cooldown Operations25practiceStudents execute a planned controlled reactor shutdown from full power to cold shutdown, maintaining cooldown rate within procedural limits and completing all required hold points.
  1. Pre-exercise review of the shutdown NOP, with students identifying the maximum cooldown rate limit, required hold temperatures, and safety system valve positions required during cooldown; instructor verifies student pre-exercise briefs.
  2. Full shutdown evolution on the simulator: students rotate through reactor operator, field operator communication, and shift supervisor roles, coordinating verbal communications and completing procedure steps without prompting.
  3. Students use the simulator's playback function to review their own cooldown rate trend, identify any period where rate approached the limit, and write a one-page technical narrative explaining their control actions and the physical basis for the cooldown rate restriction.
Simulator at full-power steady-state initial conditions, shutdown and cooldown NOP, cooldown rate limit reference, communication log forms, simulator playback capability, technical narrative templateCooldown rate must remain within procedural limits throughout the evolution (any exceedance = automatic fail requiring repeat); procedural step completion checklist graded by instructor—95% of steps completed correctly in sequence required to pass.
7Abnormal Operating Procedures — Instrument Failures and Off-Normal Conditions28labStudents diagnose simulated instrument failures and off-normal plant conditions, enter the correct abnormal operating procedure, and restore or stabilize the plant within the required response time.
  1. Instructor inserts five discrete instrument failure scenarios sequentially (e.g., failed-high coolant temperature indication, spurious low-pressure trip signal, inoperable level transmitter) while students are at the panel; students must identify the failure mode, consult the annunciator response procedure, and take appropriate conservative action.
  2. Students practice the symptom-based diagnostic method: given a set of abnormal indications, they determine whether the plant condition is a primary system anomaly or an instrument anomaly and document their reasoning on a structured diagnostic worksheet before selecting an AOP.
  3. Team exercise in which a crew of three students manages a reactor coolant system high-temperature AOP while maintaining communications with a simulated field operator (instructor role-playing); crew debriefs on task distribution and communication quality.
Simulator with AOP injection capability, annunciator response procedures, abnormal operating procedures set, diagnostic worksheets, communication script for field operator role, stopwatch, evaluation checklistsEach student must correctly diagnose at least 4 of 5 injected failures (80%) and enter the correct AOP; time-to-first-correct-action must not exceed procedure specified response time; team communication checklist evaluated by instructor—pass requires correct crew roles and no missed critical communications.
8Emergency Operating Procedures — Loss-of-Coolant Accident Response30labStudents enter and execute the Emergency Operating Procedure for a simulated loss-of-coolant accident (LOCA), verifying automatic safety system actuation and completing manual backup actions per procedure.
  1. Pre-exercise briefing on LOCA symptom recognition: students review the EOP entry conditions, automatic actuation setpoints for emergency core cooling systems, and the safety function status trees; instructor administers a 10-question written pre-brief to confirm readiness.
  2. Full-crew LOCA simulation on the simulator: instructor initiates a small-break LOCA without announcement; students must recognize symptoms, enter the EOP, verify automatic actuations, and take prescribed manual actions while maintaining three-way communication throughout.
  3. Post-exercise hot wash conducted with simulator frozen at 20 minutes into the scenario; each student identifies two decisions they made, the procedural basis for each, and one human performance error observed in the crew during the evolution.
Simulator with LOCA injection capability, Emergency Operating Procedures (EOP) training version, safety function status tree references, pre-brief written quiz, hot-wash structured debrief form, evaluation checklist for critical tasksInstructor-graded critical task checklist: all safety-critical EOP actions must be completed correctly and in procedure sequence (any missed critical task = fail requiring immediate repeat); pre-brief quiz minimum score 80%.
9Station Blackout and Loss-of-Feedwater Emergency Response28labStudents manage simulated station blackout and loss-of-feedwater events simultaneously, prioritizing safety function restoration actions per emergency procedure while coordinating with simulated plant staff.
  1. Instructor presents the technical basis for station blackout regulatory requirements and the role of alternate AC power sources and battery-backed systems; students label a one-line electrical diagram showing load-shedding sequence and battery-backed bus connections.
  2. Combined station blackout plus loss-of-feedwater scenario on the simulator: students work as a crew, restoring preferred AC power per EOP while managing secondary side water inventory and communicating actions to the simulated shift supervisor.
  3. Students individually complete a post-exercise written scenario analysis: given a printout of simulator parameter trends from their exercise, they annotate the trend strips identifying when each safety function was restored and explain the significance of each restoration in one to two sentences.
Simulator with multi-failure injection, one-line electrical diagrams (training version), station blackout EOP and loss-of-feedwater EOP, simulator trend printouts, scenario analysis worksheets, communication log formsCrew evaluation checklist: correct entry into both EOPs and correct priority assignment of safety functions (pass requires all safety-critical tasks completed correctly); individual trend-strip annotation scored on a rubric—80% of identified restoration points correctly labeled and explained.
10Radiation Protection Integration in Simulator Operations24labStudents apply radiation work permit requirements, dose-rate monitoring, and ALARA decision-making during simulator scenarios that require simulated entry into radiologically controlled areas as part of plant operations.
  1. Integrated scenario: a simulated valve fails to operate from the control room and requires local manual operation; students initiate a simulated radiation work permit, review simulated radiological survey data, confirm PPE requirements, and communicate with the simulated field operator before authorizing entry—all from the control room perspective.
  2. Students practice using a simulated health physics computer display integrated into the simulator to track personnel dose in a simulated area and evaluate whether the dose projection for the job exceeds ALARA action levels, adjusting work scope or duration accordingly.
  3. Tabletop exercise with dose-rate maps: given a set of simulated survey results for three planned maintenance tasks, students rank tasks by dose impact, identify dose-reduction actions (shielding, time, distance), and document their ALARA evaluation on a standard form.
Simulator with HP computer display integration (or stand-alone RP workstation linked to simulator), simulated radiation work permit forms, simulated survey data maps, PPE reference chart, ALARA evaluation worksheet, dosimetry reference handoutRWP initiation checklist: all required fields correctly completed and consistent with simulated radiological conditions (pass/fail—any omitted required field = fail); ALARA evaluation rubric: correct ranking and at least two dose-reduction measures identified for each task (80% of evaluation criteria met to pass).
11Lockout/Tagout Coordination from the Control Room24practiceStudents coordinate a control room-initiated lockout/tagout sequence for a simulated equipment clearance order, verifying equipment isolation in the correct sequence and completing all associated simulator panel changes.
  1. Instructor reviews the relationship between control room equipment clearance orders and field LOTO execution, emphasizing the operator's responsibility to verify de-energization indication on panel instrumentation before authorizing field work; students read and annotate a sample clearance order.
  2. Students execute a simulated clearance order on the simulator: they position tagged controls to the required state, place a caution tag on the simulator panel representation, verify isolation indications are satisfied, and complete the clearance verification section of the order form.
  3. Scenario inject: a simulated field technician calls the control room and asks to remove a component from the clearance boundary; students evaluate the request against the clearance order scope, make a conservative decision, and document the communication and outcome in the shift log—following three-way communication protocol throughout.
Simulator with tagout representation capability (physical or digital tag placards), sample equipment clearance order forms, OSHA LOTO general industry standard reference (29 CFR 1910.147 summary handout), shift-log forms, communication evaluation checklistClearance order form graded for completeness and accuracy (all isolation points verified, correct status indicated)—pass requires zero missed isolation verifications; conservative decision scenario evaluated pass/fail by instructor based on whether student chose the more conservative path and documented it correctly.
12Integrated Full-Scope Simulator Practical and Post-Shift Critique36labStudents demonstrate integrated competency across a complete simulated operating shift that includes a normal power maneuver, one AOP activation, and one EOP entry, completing all associated documentation to shift-turnover standard.
  1. Students are assigned to a full crew (reactor operator, non-licensed operator, shift supervisor roles rotated) and conduct a complete simulated eight-hour shift abbreviated to a condensed three-hour exercise; the instructor injects a planned power reduction, an AOP event, and an EOP initiation during the shift without advance notice of timing.
  2. After the simulated shift, students independently complete a full shift-log covering all major evolutions, parameter trend entries, and event narratives in the format required by the simulated plant's administrative procedure; logs are submitted for grading before the critique.
  3. Structured post-shift critique: the instructor reviews the simulator recording with the full crew, pausing at each decision point; each student verbally defends their actions by citing the specific procedure step, the parameter they were monitoring, and the safety function they were protecting.
Full-scope simulator, all NOP/AOP/EOP procedures used in prior lessons, shift-log forms, simulator recording/playback capability, post-shift critique evaluation rubric, crew evaluation checklist for each roleShift-log graded on completeness rubric—pass requires all required entries present, times accurate, and event narratives factually consistent with simulator data (80% of rubric criteria met); crew evaluation checklist: no missed critical tasks in AOP or EOP phases; verbal defense evaluated pass/fail—student must correctly cite procedure basis for every challenged decision.
Assessments
AssessmentTypeWeightPass standardMethod & rubric
Simulator Operations Knowledge ExaminationWritten exam25%Minimum score of 80% (48 of 60 questions correct); any question addressing a safety-critical topic (EOP entry conditions, critical task identification, LOTO sequence) must be answered correctly—failure on any three safety-critical items requires full exam retake.A 60-question written examination covering procedure hierarchy, NOP/AOP/EOP entry conditions, safety culture traits, Technical Specification parameter limits, LOCA and station blackout response sequences, and ALARA decision-making principles. Questions are mapped to NRC Non-Licensed Operator exam content areas and NUCP Uniform Curriculum knowledge competencies.
Standard met · Safety · Time · Quality/finish · Documentation
Full-Scope Simulator Practical Skills DemonstrationSkills demonstration45%All critical tasks on the instructor evaluation checklist must be completed correctly and in procedure sequence (100% of critical tasks); non-critical procedural steps require 90% completion; any missed critical task requires the specific evolution to be repeated in full before a passing grade is awarded.Each student individually demonstrates a complete reactor startup to initial criticality and a separate EOP response evolution (LOCA or station blackout, selected by the instructor) on the full-scope simulator, with an NRC-qualified or utility-licensed training instructor evaluating performance against a standardized critical task checklist consistent with NRC license examination standards for Reactor Operator candidates.
Standard met · Safety · Time · Quality/finish · Documentation
Simulator Exercise Lab Log PortfolioLog15%Portfolio must include completed documentation from at least 10 of the 12 lessons; each shift-log entry or exercise worksheet must score 80% or higher on its individual grading rubric; any entry with a missed safety-critical item (incorrect parameter limit, wrong EOP entry condition recorded) must be corrected and resubmitted within 48 hours.Students submit a compiled portfolio of all shift-log entries, diagnostic worksheets, ALARA evaluation forms, clearance order records, and post-exercise written analyses completed across the course; the portfolio is reviewed holistically for completeness, technical accuracy, and professional documentation quality consistent with plant administrative procedure standards.
Standard met · Safety · Time · Quality/finish · Documentation
Integrated Safety Compliance CheckSafety audit15%Pass requires 100% compliance on all safety-critical behavioral items (three-way communication, PPE use, conservative decision when prompted, and LOTO verification sequence); a single failure on any safety-critical item is a fail and requires remediation and re-check before the student may proceed to the Maintenance course.A structured behavioral observation conducted by the instructor during the Lesson 12 integrated shift exercise, using a standardized safety compliance checklist that evaluates three-way communication adherence, correct PPE identification for simulated radiological conditions, LOTO coordination sequence accuracy, and at least one conservative decision-making demonstration when the instructor presents an ambiguous plant condition.
Standard met · Safety · Time · Quality/finish · Documentation
BLD-NUCL84-08 Trade course

Nuclear Plant Maintenance: Procedures, Equipment, and Reliability

313 hr · $6,480 COMPLIMENTARY

This course develops the knowledge and hands-on skills required to perform corrective, preventive, and predictive maintenance on nuclear power plant systems and components in compliance with NRC regulations, plant technical specifications, and quality assurance requirements. Students practice work order execution, equipment alignment, valve and pump maintenance, electrical and instrumentation work, and post-maintenance testing using industry-standard procedures. Emphasis throughout is on human performance tools, radiological work controls, lockout/tagout, and the conservative decision-making culture mandated by NRC safety culture policy.

Outcomes
Course text

This course develops the knowledge and hands-on skills required to perform corrective, preventive, and predictive maintenance on nuclear power plant systems and components in compliance with NRC regulations, plant technical specifications, and quality assurance requirements. Students practice work order execution, equipment alignment, valve and pump maintenance, electrical and instrumentation work, and post-maintenance testing using industry-standard procedures. Emphasis throughout is on human performance tools, radiological work controls, lockout/tagout, and the conservative decision-making culture mandated by NRC safety culture policy.

How the course runs. 12 blocks: Maintenance Philosophy, Work Management, and the Nuclear Work Order Process; Human Performance Tools in Maintenance: Procedure Use, Pre-Job Briefing, and Self-Checking; Lockout/Tagout and Nuclear Plant Clearance Order Procedures; Reading and Using Maintenance Drawings: P&IDs, One-Lines, and Isometrics; Valve Maintenance: Types, Disassembly, Inspection, Packing, and Reassembly; Pump Maintenance: Alignment, Mechanical Seals, Bearing Inspection, and Lubrication; Electrical Maintenance: Motor Testing, Cable and Termination Inspection, and MCC Work; Predictive Maintenance: Vibration Analysis, Thermography, and Oil Sampling; Radiological Work Permits and ALARA Maintenance Planning; Post-Maintenance Testing: Restoration, Functional Testing, and Returning Equipment to Operable Status; Maintenance Quality Assurance, Condition Reports, and Continuous Improvement; Integrated Maintenance Evolution: Full Work Package Execution on a Plant System Mock-Up.

What competent looks like. Execute a plant maintenance work order from initiation through post-maintenance testing while following written procedures step-by-step and documenting all steps accurately. Apply lockout/tagout and clearance order procedures to isolate mechanical, electrical, and radiological hazards before beginning maintenance on plant equipment. Perform preventive and corrective maintenance tasks on valves, pumps, heat exchangers, motors, and instrument loops using correct tools, torque specifications, and manufacturer guidance. Interpret maintenance-related plant drawings including P&IDs, electrical one-line diagrams, and isometric piping drawings to locate, identify, and return equipment to its correct configuration. Conduct basic predictive maintenance data collection including vibration readings, thermographic inspection, and oil analysis sampling, and explain how results trigger work orders. Apply NUCP Uniform Curriculum competency areas related to maintenance and demonstrate radiation protection controls (ALARA, RWP compliance) during all simulated maintenance evolutions.

Lessons · 12 blocks
#LessonHrTypeObjectiveActivitiesMaterialsCheck
1Maintenance Philosophy, Work Management, and the Nuclear Work Order Process22.5theoryStudents will explain the corrective, preventive, and predictive maintenance categories, describe the plant work order lifecycle from identification to closeout, and identify how each step supports operability and NRC compliance.
  1. Read and annotate a sample nuclear plant maintenance work order package including the work order form, associated procedures, and required attachments; identify each required field and explain its purpose.
  2. Participate in a facilitated discussion comparing a maintenance event from a publicly available NRC inspection report with the correct work management process steps that should have been followed, identifying where the process broke down.
  3. Complete a written exercise in which students sequence the steps of the work order lifecycle—from deficiency identification through post-maintenance testing and closeout—and justify the regulatory or quality assurance basis for each step using the applicable 10 CFR 50 Appendix B quality assurance criteria (described generally, not by specific subsection number).
Sample nuclear plant work order package (redacted or training version), NRC inspection report excerpts (publicly available from NRC.gov), 10 CFR 50 Appendix B quality assurance criteria reference, whiteboard, student workbooksWritten quiz requiring students to correctly sequence and label all major work order lifecycle steps and identify the QA basis for at least four steps; passing score 75% or higher.
2Human Performance Tools in Maintenance: Procedure Use, Pre-Job Briefing, and Self-Checking20.5demoStudents will demonstrate proper procedure-use techniques including place-keeping, self-check (STAR), peer check, and two-person verification, and conduct a compliant pre-job briefing for a simulated maintenance task.
  1. Instructor demonstrates correct procedure use with place-keeping marker on a printed maintenance procedure while narrating each STAR (Stop, Think, Act, Review) step; students then replicate the technique on a second procedure at their workstations.
  2. In pairs, students role-play a pre-job briefing for a valve packing replacement task using a provided briefing checklist covering scope, hazards, roles, stop-work authority, and contingencies; instructor evaluates and provides structured feedback.
  3. Students intentionally identify and flag five deliberate errors embedded in a printed procedure (wrong valve tag number, missing torque value, reversed sequence step, omitted sign-off block, incorrect tool specification) and document corrections using a condition report form.
Sample maintenance procedures (valve and pump focus), place-keeping markers, pre-job briefing checklist, condition report forms, embedded-error procedure handouts, INPO AP-928 human performance reference (or equivalent industry document)Instructor observation checklist: student correctly performs STAR on at least three consecutive procedure steps without prompting, and pre-job briefing covers all required checklist elements; both items must be marked satisfactory to pass.
3Lockout/Tagout and Nuclear Plant Clearance Order Procedures26.5labStudents will prepare, apply, and release a lockout/tagout clearance order on a simulated plant electrical and mechanical system, verifying zero energy state before performing a mock maintenance task.
  1. Using a training-room mock-up of a motor-driven pump, students identify all energy sources (electrical, mechanical, pneumatic, hydraulic), list each on a clearance order form, and select the correct lock, tag, or blank for each isolation point before applying them in correct sequence.
  2. Students perform the required verification steps to confirm zero energy state: attempt to start the motor via the control switch, manually verify valve positions, check pressure gauges, and document each verification on the clearance order.
  3. Students demonstrate the release sequence: remove personal locks in reverse application order, restore all isolation points, remove tags, obtain supervisor release signature, and brief the operator on equipment restoration—all steps documented on the clearance order form.
Training-room motor-driven pump mock-up, lockout hasps, personal safety padlocks, danger tags, blanks, clearance order forms, multimeter (for zero-voltage verification step), OSHA 29 CFR 1910.147 reference card, plant clearance procedure (training version)Student completes the full clearance order correctly with no isolated energy sources missed, confirms zero energy state with documented evidence, and releases the clearance in correct order; any missed isolation point is an automatic fail requiring full repeat.
4Reading and Using Maintenance Drawings: P&IDs, One-Lines, and Isometrics22.5theoryStudents will locate and identify components, trace flow paths, and determine correct post-maintenance valve lineups using piping and instrumentation diagrams, electrical one-line diagrams, and isometric piping drawings.
  1. Using a training set of P&IDs for a generic PWR residual heat removal system, students trace the flow path from the pump suction through the heat exchanger to the reactor coolant system, labeling each valve and instrument by tag number and noting normal operating position.
  2. Students use an electrical one-line diagram to trace power supply from the 4160 V bus through the motor control center to a specific pump motor, identifying each protective relay and disconnect and recording the information on a component location worksheet.
  3. Given an isometric drawing of a pump discharge piping section, students identify the type, size, and orientation of five fittings, determine the direction of flow, and list the correct gasket and bolt specifications for one flanged joint; answers are compared against an answer key and discrepancies discussed.
Training P&ID sets (generic PWR or training reactor), electrical one-line diagram training set, isometric piping drawing examples, component location worksheets, drawing symbol legend reference, ASME/ANSI drawing standards referenceDrawing interpretation worksheet scored against answer key; student must correctly identify at least 80% of components, flow paths, and specifications across all three drawing types to pass.
5Valve Maintenance: Types, Disassembly, Inspection, Packing, and Reassembly28labStudents will disassemble, inspect, repack, and reassemble a gate valve and a globe valve using a written maintenance procedure, applying correct torque values and documenting all steps on a maintenance data sheet.
  1. Following a written disassembly procedure, students remove the bonnet from a 2-inch gate valve using the correct wrench sequence, inspect the disc, seats, and stem for wear and scoring, record findings on a condition assessment form, and determine whether the component is serviceable based on provided acceptance criteria.
  2. Students remove old packing from the gate valve stuffing box, measure the correct packing cross-section using calipers, cut new graphite packing rings to the correct length using the 45-degree diagonal cut method, install rings in the correct staggered orientation, and set initial packing gland torque per the procedure.
  3. Students reassemble the valve, torque bonnet bolts to the specified value in a cross-pattern sequence using a calibrated torque wrench, perform a hydrostatic bench leak test using the training test rig, and complete all sign-off blocks on the maintenance data sheet before presenting the finished work order package to the instructor.
2-inch gate valve (training use), 2-inch globe valve (training use), graphite packing rings, calibrated torque wrench, calipers, maintenance procedure (valve specific, training version), maintenance data sheet, hydrostatic bench test rig, pipe wrenches, assorted hand tools, PPE (safety glasses, gloves)Instructor inspects final valve assembly, reviews torque values on data sheet, and observes hydrostatic test; no visible packing leak at test pressure and all data sheet sign-offs complete; any untorqued fastener or undocumented step is a fail.
6Pump Maintenance: Alignment, Mechanical Seals, Bearing Inspection, and Lubrication28labStudents will perform a dial-indicator shaft alignment check on a motor-pump coupling, inspect and replace a mechanical seal, check bearing clearances, and lubricate bearings per the manufacturer's procedure.
  1. Using a small centrifugal training pump and motor set, students mount a dial indicator on the coupling, rotate the shaft to take angular and parallel misalignment readings at four positions (12, 3, 6, and 9 o'clock), record readings on an alignment data sheet, and determine whether shim corrections are needed based on published acceptance tolerances.
  2. Students disassemble the pump seal chamber, remove the worn mechanical seal, clean all mating surfaces, install a replacement seal cartridge using correct O-ring lubrication and compression technique, and reassemble the seal chamber to procedure-specified torque.
  3. Students use a feeler gauge to check radial bearing clearance on the pump bearing housing, compare the measurement to the acceptance band in the manufacturer's manual, add the correct type and quantity of grease to the bearing housing using a hand grease gun, and complete the lubrication record on the PM checklist.
Training centrifugal pump and motor set with flexible coupling, magnetic-base dial indicator set, feeler gauge set, mechanical seal cartridge (replacement), compatible O-ring lubricant, calibrated torque wrench, grease gun, compatible bearing grease, alignment data sheet, PM checklist, manufacturer's manual excerpts, PPEAlignment readings within acceptable tolerance and documented on data sheet; seal installation verified visually by instructor with no pinched O-ring; bearing clearance and lubrication quantity recorded correctly; all PM checklist sign-offs present; failing any single item requires the task to be repeated.
7Electrical Maintenance: Motor Testing, Cable and Termination Inspection, and MCC Work26.5demoStudents will use a megohmmeter and clamp-on ammeter to perform insulation resistance and load current tests on a training motor, inspect cable terminations in a mock motor control center, and document results on a PM data sheet.
  1. Instructor demonstrates megohmmeter use on a training motor winding: connecting leads to each winding terminal and ground, applying the test voltage for the specified duration, reading and recording the insulation resistance value, and comparing the result to the minimum acceptance criterion from the manufacturer's manual; students then repeat the test independently.
  2. Using a clamp-on ammeter, students measure the running current on each phase of the motor during a no-load test run, compare the readings to the nameplate full-load amperage, calculate the percentage of full-load current, and flag any phase imbalance exceeding the acceptance limit listed in the PM procedure.
  3. In pairs, students inspect ten cable terminations in a mock MCC cubicle, checking for loose connections (using a calibrated torque wrench), corrosion, damaged insulation, and correct labeling; each finding is recorded on an inspection log and a condition report is initiated for any unsatisfactory finding.
Training three-phase motor, megohmmeter (appropriate voltage range for motor class), clamp-on ammeter, mock MCC cubicle with training connections, calibrated torque wrench, PM data sheet, condition report forms, electrical safety PPE (insulated gloves rated to voltage class, safety glasses, arc flash face shield for applicable steps), NFPA 70E referenceInstructor reviews completed PM data sheet for correct megohmmeter readings, current measurements, and phase imbalance calculation; all ten termination findings are entered correctly; condition report initiated for any deficiency; 80% accuracy on data sheet values required to pass.
8Predictive Maintenance: Vibration Analysis, Thermography, and Oil Sampling20.5demoStudents will collect vibration data on a rotating equipment training stand, perform a thermal scan on a training electrical panel, and take an oil sample from a training gear box, then interpret each data set using provided acceptance criteria.
  1. Using a portable vibration data collector, students measure overall vibration velocity at three bearing locations on a training motor-pump set, compare readings to the applicable ISO vibration severity zone boundaries, and determine whether the reading falls in the 'good,' 'satisfactory,' 'unsatisfactory,' or 'unacceptable' zone; findings are entered into the predictive maintenance data log.
  2. Instructor demonstrates use of a thermal imaging camera on a training electrical panel with one intentionally warm connection; students scan the same panel, identify the thermal anomaly, record the temperature differential, and classify severity using the provided thermographic inspection guideline (temperature rise above ambient bands).
  3. Students draw an oil sample from a training gear box using a vacuum sampling pump and clean tubing, fill the sample bottle correctly, complete the sample submittal form with equipment identification and operating hours, and explain orally how the laboratory results (viscosity, particle count, water content) would trigger a maintenance work order.
Portable vibration data collector with accelerometer, training motor-pump stand, thermal imaging camera, training electrical panel with warm connection fault, vacuum oil sampling pump, clean sampling tubing, sample bottles, sample submittal forms, ISO vibration severity standard reference (general), thermographic inspection guideline, predictive maintenance data log formsVibration readings within 10% of instructor-measured baseline values and correctly zoned; thermal anomaly correctly identified and temperature differential recorded; oil sample bottle filled and labeled without contamination as confirmed by instructor observation; all three tasks must be satisfactory to pass.
9Radiological Work Permits and ALARA Maintenance Planning22.5theoryStudents will write and review a radiological work permit for a simulated maintenance task in a controlled radiological area, applying ALARA principles including dose estimates, stay times, shielding options, and remote tooling alternatives.
  1. Given a scenario describing a valve packing replacement task in a posted high-radiation area with a known dose rate, students calculate the expected dose for the task at two work rates, determine the stay time limit that keeps individual dose within the planned work permit limit, and record the calculation on the RWP planning worksheet.
  2. Students draft a complete radiological work permit for the same scenario, entering all required fields: work description, dose rate survey data, contamination survey data, required dosimetry, required respiratory protection decision, and applicable ALARA measures including pre-staging tools and using a second person as a dose-rate lookout.
  3. Class reviews two completed RWPs—one correctly prepared and one with five intentional deficiencies (missing survey, wrong dosimetry requirement, ALARA measure omitted, incorrect posting requirement, wrong protective clothing level)—and identifies all deficiencies in the flawed RWP, justifying each correction against regulatory and procedural requirements.
RWP forms (training versions), ALARA planning worksheet, dose rate scenario cards, 10 CFR 20 general reference, plant radiation protection procedure excerpts (training versions), RWP example sets (correct and deficient), student workbooksStudent's completed RWP is scored against a grading rubric covering all required fields; stay time calculation must be correct within 5%; at least four of five deficiencies must be identified in the review exercise; overall score 75% or higher to pass.
10Post-Maintenance Testing: Restoration, Functional Testing, and Returning Equipment to Operable Status22.5practiceStudents will restore a simulated plant system to its correct valve lineup following a maintenance evolution, perform required functional tests per a written procedure, and declare the component operable using the criteria defined in the maintenance work order.
  1. Using the training plant P&ID and a post-maintenance restoration checklist, students verify all tools have been removed, temporary connections disconnected, and all isolation points returned to their normal operating position; each valve position is confirmed against the normal system lineup sheet and initialed on the checklist.
  2. Students perform a step-by-step functional test of a training pump per the written post-maintenance test procedure: start the pump from the local control station, verify discharge pressure rises to the specified band, check for packing or seal leaks, measure and record running current, and confirm proper bearing temperature after a timed run period.
  3. Students complete the work order closeout package: enter all test data on the post-maintenance test data sheet, record the as-found and as-left condition of each component touched during maintenance, obtain a peer check signature, and write a one-paragraph operability determination statement using the acceptance criteria from the work order.
Training pump system with instrumentation, normal system lineup sheet, post-maintenance test procedure (training version), post-maintenance test data sheet, work order closeout package forms, calibrated pressure gauge, clamp-on ammeter, infrared thermometer, PPEAll valve positions verified against lineup sheet with no missed item; all required test parameter readings recorded and within acceptance bands; operability determination statement contains all required elements; any missed isolation point restoration or out-of-band test parameter not flagged is an automatic fail.
11Maintenance Quality Assurance, Condition Reports, and Continuous Improvement28practiceStudents will initiate a condition report for a maintenance-related deficiency, perform an apparent cause evaluation, and develop a corrective action that addresses the root cause using a structured cause analysis method.
  1. Given a scenario describing a pump that failed its post-maintenance test due to incorrect packing installation (the wrong packing material was used because the work order referenced an outdated revision of the procedure), students initiate a condition report by documenting the deficiency description, equipment tag, date, time, and immediate operability impact using the condition report form.
  2. Students apply a structured apparent cause evaluation method (such as the 'five whys' technique) to the packing material scenario, tracing the causal chain from the immediate cause (wrong packing installed) back through contributing causes (outdated procedure used, no revision check step in the work package preparation process) and identifying the apparent cause.
  3. Students write a corrective action proposal that addresses the apparent cause—specifically, adding a procedure revision verification step to the work package preparation checklist—and identify any extent-of-condition check needed (other work packages that may reference the same outdated procedure); the proposal is presented to a peer group for a brief critique.
Condition report form (training version), cause evaluation worksheet, 'five whys' reference guide, sample completed condition reports for comparison, student workbooks, whiteboard for group discussionCondition report is complete with all required fields; causal chain correctly identifies at least two contributing causes and the apparent cause; corrective action directly addresses the apparent cause; peer group and instructor must both agree the corrective action is plausible; 75% score on instructor rubric to pass.
12Integrated Maintenance Evolution: Full Work Package Execution on a Plant System Mock-Up45labStudents will execute a complete maintenance work package—from pre-job briefing through post-maintenance testing and closeout—on a multi-component plant system training mock-up, demonstrating all competencies developed in the course.
  1. Each student team receives a complete maintenance work order package for a corrective maintenance task on the training mock-up (which incorporates a pump, two valves, motor, and instrumentation); teams conduct a pre-job briefing covering scope, hazards, radiological controls, LOTO steps, and stop-work authority before any hands-on work begins.
  2. Teams execute the maintenance task step-by-step under procedure control, performing LOTO, disassembly, repair or replacement, reassembly to torque specification, and restoration in correct sequence while the instructor observes and evaluates human performance tool use, documentation accuracy, and team communication throughout.
  3. Teams complete the post-maintenance test per the written procedure, record all data on the test data sheet, write the operability determination, and present the closed work order package to the instructor for a final review; any deficiency identified during the review must be corrected and the documentation resubmitted before the team receives a passing grade.
Multi-component plant system training mock-up (pump, valves, motor, instrumentation), complete maintenance work order package (training version), LOTO equipment, calibrated torque wrench, dial indicator set, calipers, replacement packing and seals, clamp-on ammeter, infrared thermometer, pressure gauges, all required PPE, condition report forms, post-maintenance test data sheetsInstructor uses a standardized evaluation rubric covering 10 categories: pre-job briefing completeness, LOTO application correctness, procedure adherence (no skipped steps), torque values documented, human performance tool use observed, radiological control compliance, post-maintenance test data complete and within acceptance bands, operability determination written, work order package complete, no unresolved deficiencies; student must score satisfactory in at least 8 of 10 categories to pass.
Assessments
AssessmentTypeWeightPass standardMethod & rubric
Maintenance Knowledge ExaminationWritten exam25%75% or higher on a 80-question written examA proctored written exam covering work order lifecycle, maintenance categories, LOTO principles, P&ID and one-line diagram interpretation, valve and pump maintenance theory, predictive maintenance data interpretation, post-maintenance testing requirements, and condition reporting and corrective action processes; questions are drawn from all lesson topics and mapped to NUCP Uniform Curriculum maintenance competency areas and NRC Non-Licensed Operator preparation knowledge areas.
Standard met · Safety · Time · Quality/finish · Documentation
Practical Maintenance Skills DemonstrationSkills demonstration45%Satisfactory rating on all critical steps; any critical step failure requires a full repeat of that taskEach student individually performs three timed practical tasks drawn by lot from the course lab evolutions (valve repack, pump alignment check, LOTO application, or motor megohmmeter test); the instructor evaluates each task using a standardized critical-step checklist, and the student must complete all steps in correct procedural order, apply correct torque or measurement technique, and complete the associated data sheet without coaching.
Standard met · Safety · Time · Quality/finish · Documentation
Maintenance Lab LogLog15%Complete entries for all 12 lessons with satisfactory rating on 90% of entries; any safety documentation deficiency requires correction before passingStudents maintain a bound lab log throughout the course recording the objective, procedure steps performed, all measured data, acceptance criteria comparisons, any condition found out of specification, corrective actions taken, and a brief reflection on human performance tool use for every lab and practice lesson; the log is reviewed at lessons 6 and 12 and must demonstrate procedural rigor, accurate data recording, and complete sign-off documentation consistent with nuclear quality assurance standards.
Standard met · Safety · Time · Quality/finish · Documentation
Safety and Radiological Controls Compliance CheckSafety audit15%Zero critical safety violations observed; one non-critical finding allowed with documented corrective actionThe course safety officer and lead instructor conduct a formal observation of each student during the integrated maintenance evolution (Lesson 12), evaluating correct PPE selection and use, LOTO application with no missed energy sources, radiological work permit adherence, proper contamination control (no spreading contamination outside the designated work area), and correct use of stop-work authority when an unexpected condition is introduced by the instructor; any critical safety violation (missing energy isolation, PPE removal in a radiological area, or bypassing a procedure step) results in an immediate task stop and automatic fail requiring full remediation.
Standard met · Safety · Time · Quality/finish · Documentation
BLD-NUCL84-09 Capstone

Capstone Project: Integrated Nuclear Plant Systems Analysis & Defense

432 hr · $4,320 COMPLIMENTARY

Students synthesize all prior coursework by completing a full-scope, documented plant systems analysis project centered on a realistic nuclear power plant scenario, integrating reactor physics, radiation protection, instrumentation and control, maintenance planning, and NRC regulatory compliance. The capstone culminates in a formal written technical report and an oral defense before a panel of instructors and, where available, an industry subject-matter expert. Successful completion demonstrates readiness for the NRC Non-Licensed Operator pathway, the NUCP credential, NRRPT eligibility requirements, and supervised RO license candidacy.

Outcomes
Course text

Students synthesize all prior coursework by completing a full-scope, documented plant systems analysis project centered on a realistic nuclear power plant scenario, integrating reactor physics, radiation protection, instrumentation and control, maintenance planning, and NRC regulatory compliance. The capstone culminates in a formal written technical report and an oral defense before a panel of instructors and, where available, an industry subject-matter expert. Successful completion demonstrates readiness for the NRC Non-Licensed Operator pathway, the NUCP credential, NRRPT eligibility requirements, and supervised RO license candidacy.

How the course runs. 4 blocks: Scenario Assignment, Scoping, and Project Planning; Technical Analysis: Systems, Radiation Protection, and Maintenance Package Development; Report Compilation, Corrective Action Write-Up, and Defense Preparation; Final Defense, Panel Review, and Reflection.

What competent looks like. Produce a complete, NRC-compliant plant system analysis package—including system descriptions, P&ID mark-ups, and abnormal operating procedure (AOP) walk-throughs—for an assigned plant system or scenario to a professional technical-writing standard. Apply radiation protection principles, dose calculations, and ALARA planning to the assigned scenario, demonstrating competency areas aligned with NRRPT exam domains. Develop and justify a lockout/tagout and work-order package for a maintenance task within the scenario, meeting OSHA 29 CFR 1910.147 requirements and plant technical specification constraints. Evaluate the assigned scenario against applicable NRC regulatory requirements and document any identified nonconformances with a corrective action recommendation consistent with 10 CFR Part 50 Appendix B quality assurance principles. Defend all technical decisions verbally before a review panel, responding accurately to examiner questions on reactor physics, system interactions, and safety culture principles. Demonstrate professional documentation practices by submitting a final project binder that meets NEI NUCP Uniform Curriculum formatting and completeness standards.

Lessons · 4 blocks
#LessonHrTypeObjectiveActivitiesMaterialsCheck
1Scenario Assignment, Scoping, and Project Planning80theoryGiven an assigned plant scenario, the student will produce a documented project plan that identifies the affected systems, applicable regulatory requirements, radiation zones, and a realistic work breakdown structure with milestones.
  1. Receive and analyze the assigned scenario package (instructor-prepared, modeled on a pressurized-water reactor or boiling-water reactor training scenario); identify the primary and interfacing plant systems using provided P&IDs, system descriptions, and the plant technical specifications excerpt, then produce a one-page scope-of-work statement.
  2. Research applicable NRC regulatory bases (10 CFR Part 50 and associated appendices, plant technical specifications, and selected regulatory guides) to list every regulatory touchpoint for the scenario; record findings in a regulatory compliance matrix spreadsheet that will become Section 2 of the final report.
  3. Create a project schedule using a Gantt chart or equivalent tool, assigning hours to each major deliverable (system analysis, ALARA plan, LOTO package, corrective action write-up, report draft, and defense preparation); submit the plan for instructor approval before proceeding.
Instructor-prepared scenario packet, sample P&IDs and system description excerpts, 10 CFR Part 50 (publicly available NRC source), NEI NUCP Uniform Curriculum reference binder, plant technical specification excerpts, project planning software or spreadsheet application, NRRPT Candidate Handbook (for domain cross-reference)Instructor approves the scope statement and regulatory compliance matrix; pass requires all primary systems correctly identified, at least five regulatory touchpoints documented with accurate CFR citations, and a Gantt chart with realistic milestone dates. Incomplete or inaccurate scope requires revision before Lesson 2 begins.
2Technical Analysis: Systems, Radiation Protection, and Maintenance Package Development192labThe student will complete the full technical body of the capstone—system functional analysis, ALARA dose planning, and a compliant LOTO/work-order package—to a standard that could serve as a training document in a licensed nuclear facility.
  1. Perform a system functional analysis for the primary assigned system: describe normal operating parameters, safety function, major components (pumps, valves, heat exchangers, instrumentation), and system interactions; mark up a provided P&ID to show system boundaries, isolation points, and instrument tag numbers; write this up as Section 3 of the technical report using the NEI NUCP document format, minimum eight pages with labeled figures.
  2. Develop an ALARA radiation work permit (RWP) analog for the maintenance task embedded in the scenario: calculate estimated dose rates using provided radiological survey data and simple point-source or buildup-factor methods taught in Course 5; specify dosimetry requirements, PPE (anti-contamination clothing, respiratory protection if warranted), stay times, dose goals, and posting requirements consistent with 10 CFR Part 20 dose limits; have a peer review the RWP analog using an instructor-supplied checklist, then revise and finalize as Section 4 of the report.
  3. Produce a complete LOTO package for the maintenance isolation required by the scenario: list every energy source (electrical, mechanical, thermal, pneumatic, hydraulic) to be controlled; write step-by-step isolation and restoration procedures referencing specific system valve numbers from the P&ID; include a verification checklist and a danger tag log; review the package against OSHA 29 CFR 1910.147 requirements using an instructor-supplied audit form and correct any deficiencies before submission.
Scenario P&IDs (instructor-prepared, generic plant-model based), radiological survey data sheets, 10 CFR Part 20 dose limit tables, NEI NUCP Uniform Curriculum reference binder, OSHA 29 CFR 1910.147 standard (publicly available), sample RWP and LOTO forms, scientific calculator, dose-rate calculation worksheets from Course 5, peer-review checklist, word-processing and spreadsheet softwareInstructor grades each subsection using a rubric with three domains—technical accuracy, regulatory compliance, and professional formatting—each scored 0–4; a total score of 30 out of 36 (83%) or higher is required to proceed. LOTO packages missing any energy source or lacking a verification step are automatically returned for correction regardless of overall score. ALARA dose calculations must be within ±20% of the instructor's reference solution.
3Report Compilation, Corrective Action Write-Up, and Defense Preparation100practiceThe student will assemble the complete technical report, write a 10 CFR Part 50 Appendix B-based corrective action document for a seeded deficiency in the scenario, and rehearse the oral defense to the point of confident, accurate response to panel questions.
  1. Integrate all prior sections into a single, formatted technical report: cover page, table of contents, executive summary (maximum one page), regulatory compliance matrix (Section 2), system functional analysis (Section 3), ALARA/RWP analog (Section 4), LOTO package (Section 5), and corrective action document (Section 6); apply NEI NUCP Uniform Curriculum document conventions throughout; submit a complete draft to the instructor for a formal red-line review at least one week before the defense date.
  2. Write the corrective action document (Section 6) for the seeded nonconformance embedded in the scenario (e.g., an out-of-calibration instrument, an expired surveillance test, or a procedure deviation): identify the condition adverse to quality, perform a basic apparent cause evaluation using the five-whys method, propose an immediate corrective action and a long-term preventive action, and assign a priority level consistent with the plant's corrective action program structure as described in 10 CFR Part 50 Appendix B; limit to three to five pages.
  3. Conduct two full mock defenses: one with a classmate as questioner using an instructor-supplied question bank covering reactor physics, radiation protection, regulatory compliance, and maintenance topics from all prior courses; one with the instructor serving as a panel member asking at least ten unannounced technical questions; record both sessions if equipment permits and self-evaluate using the oral defense rubric so weaknesses can be addressed before the graded event.
Complete draft report from Lesson 2, instructor red-line markup, NEI NUCP Uniform Curriculum formatting guide, 10 CFR Part 50 Appendix B text (publicly available), five-whys worksheet, oral defense rubric (instructor-supplied), question bank covering Courses 1–8 key topics, word-processing software, presentation slides (optional, student's choice), recording device (optional)Instructor approves the complete draft report as 'ready to defend' only if all six sections are present, the executive summary accurately reflects the body, and no unresolved red-line comments remain on safety-critical items (LOTO isolation steps, dose limit compliance, or regulatory citations). Students who fail the mock defense by scoring below 70% on the question bank must complete an additional coached session before the graded defense.
4Final Defense, Panel Review, and Reflection60fieldThe student will present and defend the completed capstone project before a panel, respond accurately to technical questions across all program subject areas, and produce a written professional reflection connecting the project to career readiness and lifelong learning in the nuclear industry.
  1. Deliver a 20–30 minute structured oral presentation to the review panel (minimum two instructors; industry guest if available) summarizing the scenario, the systems analyzed, the ALARA strategy, the LOTO package logic, and the corrective action outcome; use prepared visual aids (whiteboard diagrams, printed report pages, or slides) and field a minimum of 15 minutes of technical questions from the panel without referring to notes except to cite a specific regulatory reference.
  2. Participate in a post-defense debrief in which the panel provides verbal and written feedback on technical accuracy, depth of regulatory knowledge, communication clarity, and professional bearing; receive the panel's scored rubric and a pass/needs-revision determination; if a conditional pass is issued, complete specified written corrections to the report within five business days.
  3. Write a two- to three-page professional reflection document addressing: (a) which program courses most directly informed each section of the capstone, (b) one technical area where the student's knowledge grew most during the project, (c) how the work connects to the NRC Non-Licensed Operator role and potential RO license pathway, and (d) a personal continuing-education plan for the first two years of employment (e.g., NRRPT examination preparation, utility-sponsored RO training, NEI courses).
Final bound technical report (one copy per panel member), oral defense rubric, panel scoring sheets, presentation materials (student-prepared), NEI NUCP competency checklist (for panel reference), reflection prompt handout, 10 CFR Part 50 reference copy available at the defense tablePanel scores the defense on a rubric with five categories: technical accuracy of report content (25 points), regulatory and safety compliance (25 points), quality of oral communication and question responses (20 points), document professionalism and completeness (20 points), and corrective action quality (10 points); passing score is 75 out of 100. A score of 65–74 earns a conditional pass requiring written corrections. A score below 65 requires a re-defense scheduled within 30 days. The reflection document is graded pass/fail on completeness; all four required elements must be present.
Assessments
AssessmentTypeWeightPass standardMethod & rubric
Capstone Technical ReportProject60%83% (30/36 on the section rubric) with no unresolved safety-critical deficiencies; LOTO and dose-calculation sections must individually meet minimum accuracy thresholds before overall score is computedA complete, six-section technical report produced individually by the student that includes a system functional analysis with marked-up P&ID, an ALARA radiation work permit analog with supporting dose calculations, a full LOTO isolation and restoration package compliant with OSHA 29 CFR 1910.147, and a corrective action document referencing 10 CFR Part 50 Appendix B; the report is formatted to NEI NUCP Uniform Curriculum standards and serves as the primary project deliverable evaluated for technical depth, regulatory accuracy, and professional documentation quality.
Meets specification · Within estimate · Workmanship · Safety · Documentation
Capstone Project PortfolioPortfolio20%All six report sections present and complete; no outstanding instructor red-line comments on safety-critical items; reflection document addresses all four required elements; overall portfolio rated 'complete' by instructor before defense dateThe portfolio is the assembled binder submitted to the review panel and contains the final technical report, the peer-review checklist from the ALARA section, the mock-defense self-evaluation forms, the instructor red-line markup with documented student responses, and the professional reflection document; it demonstrates the student's growth across the entire program and readiness for the externship and credential examinations.
Completeness · Organization · Evidence quality
Oral DefenseOral / panel20%75 out of 100 points on the panel rubric; conditional pass (65–74) requires written corrections within five business days; below 65 requires re-defense within 30 daysA 20–30 minute presentation followed by a minimum 15-minute technical question session conducted before a panel of at least two instructors and, where available, an industry subject-matter expert; the panel evaluates technical accuracy, regulatory and safety compliance, communication clarity, document quality, and corrective action reasoning using a standardized rubric, providing written feedback that directly informs the student's exam preparation and externship readiness.
Explains decisions · Answers technical questions · Professional communication
BLD-NUCL84-10 Externship / clinical

Externship / Worksite Placement at a Nuclear Facility

648 hr · $2,590 COMPLIMENTARY

Students complete 648 supervised hours at a licensed nuclear power plant or related nuclear facility, applying classroom knowledge under the direct oversight of qualified nuclear professionals. Rotations cover plant operations, radiation protection, instrumentation and control, and maintenance activities, mirroring the job duties assessed by the NRC Non-Licensed Operator, NRRPT, and NUCP credentials. A utility-assigned supervisor evaluates performance against industry competency standards throughout the placement.

Outcomes
Course text

Students complete 648 supervised hours at a licensed nuclear power plant or related nuclear facility, applying classroom knowledge under the direct oversight of qualified nuclear professionals. Rotations cover plant operations, radiation protection, instrumentation and control, and maintenance activities, mirroring the job duties assessed by the NRC Non-Licensed Operator, NRRPT, and NUCP credentials. A utility-assigned supervisor evaluates performance against industry competency standards throughout the placement.

How the course runs. 4 blocks: Site Orientation, Badging, and Radiological Access Qualification; Radiation Protection and Plant Operations Rotations; Maintenance, Procedure Compliance, and Lockout/Tagout Application; Portfolio Completion, Supervisor Evaluation, and End-of-Placement Debrief.

What competent looks like. Perform assigned non-licensed operator duties on a licensed nuclear plant site under qualified supervision, following all NRC and plant technical specifications. Apply radiation protection principles — including dosimetry, contamination surveys, and ALARA practices — in a live radiological work environment. Read, interpret, and execute plant procedures, work orders, and surveillance test instructions correctly on at least 90% of assigned tasks as rated by the site supervisor. Demonstrate proper lockout/tagout, PPE selection, and industrial safety practices in compliance with OSHA standards and plant radiation work permit requirements on every task. Communicate plant status, equipment anomalies, and radiological findings accurately in verbal shift turnover briefings and written log entries. Compile a professional externship portfolio documenting rotations, competency demonstrations, supervisor evaluations, and a personal reflection that maps experience to NUCP and NRRPT exam domains.

Lessons · 4 blocks
#LessonHrTypeObjectiveActivitiesMaterialsCheck
1Site Orientation, Badging, and Radiological Access Qualification80fieldThe student will complete all site-required access training, obtain a radiation worker badge, and demonstrate knowledge of site emergency action levels and emergency response organization roles before entering any radiologically controlled area.
  1. Complete the host utility's new-worker orientation modules covering site security, fitness-for-duty policy, emergency plan, and radiological worker training; pass all required site quizzes at the plant's minimum passing score.
  2. Accompany a health physics technician on a controlled-area walk-down, locate all emergency exits, assembly areas, and dosimeter storage stations, and record findings on a facility map sketch submitted to the supervising instructor.
  3. Participate in a simulated site emergency drill (evacuation or personnel contamination response) and correctly execute the assigned emergency role as evaluated by the site emergency coordinator using the plant's standard drill critique form.
Host utility new-worker orientation materials; site-issued TLD/dosimeter badge and electronic personal dosimeter (EPD); radiation worker training records; plant emergency plan (site-specific); OSHA 10 card (prerequisite); PPE kit including anti-contamination clothing, safety glasses, hard hat, steel-toed boots; facility map.Student receives unescorted radiation worker access authorization from the host utility (pass/fail — access granted equals pass); site quiz scores meet or exceed the plant's own passing threshold; drill critique form shows satisfactory performance in all evaluated actions.
2Radiation Protection and Plant Operations Rotations280fieldThe student will perform assigned radiation protection surveys, contamination controls, and non-licensed operator round-taking and surveillance tasks across at least three distinct plant departments under qualified supervision, meeting plant procedure requirements on each task.
  1. Rotate through health physics, plant operations (auxiliary operator rounds), and instrumentation and control departments on a schedule coordinated with the site training department; log each rotation's hours, tasks performed, and procedures used in the externship daily log submitted weekly to the program instructor.
  2. Conduct a minimum of eight independent radiation or contamination surveys using calibrated survey instruments, record results on the plant's official radiation work permit or survey form, and review findings with a certified health physics technician who signs off on each form — mapping directly to NRRPT exam domain areas covering field measurements and instrument use.
  3. Perform at least six documented auxiliary operator surveillance rounds or equipment checks (valve line-ups, pump start verifications, tank level checks) using plant-approved procedures; receive a supervisor rating on the standard competency checklist for procedure adherence, communication, and equipment identification — mapping to NUCP uniform curriculum competencies for plant operations.
Calibrated portable radiation survey instruments (Geiger-Mueller and ionization chamber types) supplied by the host facility; plant-issued electronic personal dosimeter; anti-contamination clothing and respiratory protection (as required by radiological work permit); plant operating procedures and surveillance test procedures (site-specific); externship daily log binder; site competency checklist forms; NEI NUCP competency framework reference.Supervisor competency checklist shows a satisfactory or above rating (site-defined scale) on at least 90% of evaluated task line items; all survey forms are signed off by a qualified health physics technician; daily log is current within 48 hours and reviewed by program instructor biweekly — any unsatisfactory rating triggers a documented remediation plan within five business days.
3Maintenance, Procedure Compliance, and Lockout/Tagout Application208fieldThe student will assist qualified maintenance or operations personnel in executing corrective and preventive maintenance tasks using approved work orders, correctly applying plant lockout/tagout and clearance-order processes on every assignment, with zero procedural violations as rated by the site supervisor.
  1. Shadow and assist plant maintenance technicians on a minimum of four corrective or preventive maintenance work orders for mechanical, electrical, or I&C systems; for each work order, read the entire procedure before work begins, identify all energy isolation points, and verbally brief the supervising technician on the hazard identification before touching any equipment — the technician documents the briefing quality on the site work observation form.
  2. Initiate or assist in initiating at least two plant clearance orders (lockout/tagout under the plant's equipment control program), verify the isolation by attempting to energize or operate the isolated component, and restore the clearance order at task completion; the operations supervisor verifies each step against the plant's equipment control procedure and signs the clearance record.
  3. Participate in one post-maintenance test (PMT) run-through for a system returned to service, monitor system response against acceptance criteria listed in the surveillance procedure, record data on the PMT data sheet, and present findings in a five-minute verbal debrief to the supervising engineer — mapping to NRC Non-Licensed Operator preparation requirements for understanding the relationship between maintenance and operability.
Plant work order management system access (read-level); approved plant maintenance and surveillance procedures; plant equipment control / clearance-order forms; calibrated test equipment as specified in work orders (multimeters, pressure gauges — site-supplied); personal PPE per plant radiation work permit; site work observation forms; OSHA lockout/tagout standard reference (29 CFR 1910.147 concept — specific plant procedure governs); externship daily log.Site work observation forms for all four work orders show no procedural violations and at least a satisfactory rating on hazard identification and procedure adherence; both clearance order records are signed by the operations supervisor confirming correct execution; PMT debrief is rated satisfactory by the supervising engineer on the site verbal communication rubric — any procedural violation is treated as a critical failure requiring immediate supervisor notification and documented corrective action.
4Portfolio Completion, Supervisor Evaluation, and End-of-Placement Debrief80fieldThe student will compile and present a complete externship portfolio documenting all rotations, competency demonstrations, and credential-domain mappings, and will participate in a formal end-of-placement evaluation conference with the site supervisor and program instructor.
  1. Assemble the externship portfolio including: a summary table of all rotation hours and tasks by department, copies of all signed survey forms, competency checklists, and clearance-order records, a two-page personal reflection mapping each major experience to a specific NUCP competency category or NRRPT exam domain, and a professional resume updated to reflect site experience — portfolio is submitted to the program instructor five business days before the debrief meeting.
  2. Request and receive a completed formal employer evaluation from the site supervisor using the program's standardized Employer Evaluation Form, which scores the student on safety behavior, procedure compliance, teamwork, communication, and technical knowledge on a four-point scale; the completed form is sealed and delivered directly to the program instructor.
  3. Participate in a 30-minute end-of-placement debrief conference (in person or video call) with the site supervisor and program instructor; the student presents a five-minute summary of the most challenging task encountered and the corrective actions taken, then answers questions about how the experience prepares them for the NRC Non-Licensed Operator role and future RO license pathway — responses are rated on the program's debrief rubric.
Externship portfolio binder or digital folder (organized per program template); program Employer Evaluation Form (four-point scale); NUCP Uniform Curriculum competency framework (NEI); NRRPT exam content outline; updated resume template; debrief rubric (program-issued); video conferencing access if remote.Portfolio is complete with no missing documents and personal reflection references at least six distinct NUCP or NRRPT competency areas — rated complete or incomplete by program instructor; Employer Evaluation Form averages 3.0 or higher out of 4.0 across all categories (any single category rated 1.0 triggers a remediation meeting); debrief rubric score of 75% or higher on all sections — scores below 75% require a written remediation reflection submitted within one week.
Assessments
AssessmentTypeWeightPass standardMethod & rubric
Cumulative Site Supervisor Skills Demonstration EvaluationSkills demonstration70%Average score of 3.0 or higher out of 4.0 on the program Employer Evaluation Form across all five competency categories (safety behavior, procedure compliance, teamwork, communication, technical knowledge), with no individual category scoring below 2.0; a score of 1.0 in any single category in any rotation disqualifies the student from passing until a documented remediation plan is completed and the supervisor re-rates that category.The host-site supervisor completes the program's standardized Employer Evaluation Form at the midpoint and at the conclusion of the placement, rating the student's real-time performance on safety compliance, procedure adherence, radiation protection practices, communication, and technical job knowledge observed during all rotation activities. Scores from both evaluation points are averaged; this assessment directly maps to NRC Non-Licensed Operator readiness standards and the NUCP uniform curriculum competency framework.
Competency · Safety · Attendance · Conduct · Initiative
Externship Field Log and Portfolio ReviewLog30%Portfolio is rated Complete by the program instructor (all required documents present, no unsigned forms, personal reflection addresses a minimum of six credential-domain areas with specific examples); debrief rubric score of 75% or higher; any Incomplete rating on the portfolio document checklist gives the student five business days to correct deficiencies before a final pass or fail determination is recorded.The program instructor reviews the student's externship daily log entries (submitted weekly throughout the placement) and the final assembled portfolio for completeness, accuracy of credential-domain mapping, and professionalism; the instructor also scores the end-of-placement debrief presentation using the program rubric. Together the log and portfolio constitute the documentary evidence that the student has met the supervised-hours requirement and has connected field experience to the NUCP, NRRPT, and NRC Non-Licensed Operator credential exam domains.
Complete · Verified
BLD-NUCL84-11 Exam prep

Certification Exam Preparation: NRC, NRRPT, NUCP, and OSHA Credentials

180 hr · $1,800 COMPLIMENTARY

This course systematically reviews every domain tested on the NRC Non-Licensed Operator written examination, the NRC Reactor Operator License examination, the NRRPT certification examination, the NEI NUCP competency assessment, and the OSHA 10 final quiz, using mapped content review, timed practice sets, and full-length mock exams. Students identify personal knowledge gaps through diagnostic testing, complete targeted remediation in weak areas, and build the test-taking stamina and strategy required to pass high-stakes nuclear industry credentialing exams. All practice questions are drawn from publicly available NRC examination guidance, NUREG study materials, NRRPT content outlines, and NEI curriculum frameworks.

Outcomes
Course text

This course systematically reviews every domain tested on the NRC Non-Licensed Operator written examination, the NRC Reactor Operator License examination, the NRRPT certification examination, the NEI NUCP competency assessment, and the OSHA 10 final quiz, using mapped content review, timed practice sets, and full-length mock exams. Students identify personal knowledge gaps through diagnostic testing, complete targeted remediation in weak areas, and build the test-taking stamina and strategy required to pass high-stakes nuclear industry credentialing exams. All practice questions are drawn from publicly available NRC examination guidance, NUREG study materials, NRRPT content outlines, and NEI curriculum frameworks.

How the course runs. 4 blocks: Diagnostic Assessment and Personalized Study Planning; Targeted Domain Review: NRC Written Exam and OSHA 10 Content; Targeted Domain Review: NRRPT and NUCP Competency Areas; Full-Length Mock Examinations and Final Remediation.

What competent looks like. Correctly answer at least 80 percent of practice questions in each NRC written examination content area, including reactor theory, plant systems, instrumentation and control, and emergency operating procedures. Demonstrate mastery of NRRPT examination domains—radiation physics, instrumentation, dosimetry, regulatory requirements, and radiation protection program administration—by scoring at or above the NRRPT published passing standard on a full-length mock examination. Complete a timed NUCP competency practice assessment covering all NEI Uniform Curriculum competency areas and achieve a score sufficient to meet employer qualification standards. Apply OSHA 10 general industry and construction safety concepts accurately on a timed closed-book practice quiz, earning the minimum score required for card issuance. Construct and execute a personalized remediation plan that targets identified weak domains, documents study hours, and tracks score improvement across successive practice sets. Perform successfully on full-length, timed mock examinations that simulate the format, time limits, and content weighting of each target credential, demonstrating readiness to sit the actual credentialing examinations.

Lessons · 4 blocks
#LessonHrTypeObjectiveActivitiesMaterialsCheck
1Diagnostic Assessment and Personalized Study Planning30practiceEach student administers a timed diagnostic practice test in each credential content area, analyzes the results by domain, and produces a written remediation plan that prioritizes topics by deficiency severity.
  1. Complete a timed diagnostic practice set aligned to the NRC Non-Licensed Operator and Reactor Operator written exam content outline (reactor physics, thermodynamics, plant systems, instrumentation and control, radiological fundamentals, technical specifications, and emergency procedures), then score and categorize every missed item by content domain using a provided domain-tracking spreadsheet.
  2. Complete separate shorter diagnostic sets for the NRRPT content outline (radiation physics, biological effects, instrumentation, dosimetry, regulatory and standards, and program administration) and the NEI NUCP competency areas, then repeat the domain-scoring process.
  3. Using all diagnostic data, write a two-page personalized study plan that lists each credential, ranks domains by percent correct from lowest to highest, sets a weekly study schedule for the remaining weeks of the course, and identifies specific NUREG documents, textbook chapters, and simulator debrief records to revisit for each weak domain; present the plan to the instructor for review and approval.
Printed and digital diagnostic practice question sets (drawn from NRC NUREG examination guidance and publicly released sample questions), NRRPT candidate handbook and content outline, NEI NUCP competency list, domain-tracking spreadsheet template, calculator, scratch paper, course textbooks from Courses 2–8Instructor reviews each student's completed domain-tracking spreadsheet and written study plan; plan must correctly identify all domains below 75 percent accuracy and include a specific resource and schedule entry for each deficient domain — pass requires all low-scoring domains addressed and instructor sign-off on the plan
2Targeted Domain Review: NRC Written Exam and OSHA 10 Content60theoryStudents review and apply the technical content areas most heavily weighted on the NRC Non-Licensed Operator and Reactor Operator written examinations and the OSHA 10 assessment, with emphasis on reactor fundamentals, plant systems, instrumentation logic, technical specifications, emergency operating procedures, and OSHA general safety regulations.
  1. Work through instructor-led content review sessions organized by NRC examination domain — reactor physics and neutron behavior, reactor coolant and auxiliary systems, electrical systems, instrumentation and control logic, radwaste systems, radiological fundamentals, and technical specifications — completing a minimum of 20 practice questions per domain immediately after each review session, with instructor explanation of every incorrect answer; students record corrected understanding in a personal study notebook.
  2. Participate in small-group case studies based on publicly available NRC inspection reports and event investigation summaries (available on the NRC public website) to apply technical specification and emergency operating procedure decision logic; groups present their event analysis and the applicable procedure steps to the class, receiving peer and instructor feedback.
  3. Complete a focused OSHA 10 domain review covering hazard recognition, lockout/tagout (LOTO) procedures per OSHA standards, PPE selection, electrical safety, confined space entry, fall protection, and HazCom/GHS labeling requirements; finish with a 40-question timed closed-book OSHA practice quiz and review all missed items with the instructor.
NUREG-1021 (Operator Licensing Examination Standards for Power Reactors) for exam structure guidance, plant system diagrams from Courses 3 and 4, NRC inspection report excerpts (public domain), OSHA 10 outreach curriculum materials, OSHA 29 CFR 1910 and 1926 quick-reference summaries, personal study notebooks, domain tracking spreadsheetStudent must score at least 75 percent on each domain practice question set before moving on; any domain below 75 percent triggers mandatory re-study and a second attempt on an alternate question set before the next lesson begins — instructor initials the tracking spreadsheet for each passed domain
3Targeted Domain Review: NRRPT and NUCP Competency Areas45theoryStudents review and apply all content domains on the NRRPT certification examination content outline and the NEI NUCP competency framework, achieving consistent practice-question accuracy that meets or exceeds the NRRPT and NUCP published or equivalent passing standards.
  1. Work through instructor-led sessions covering each NRRPT domain — radiation physics and atomic structure, interaction of radiation with matter, biological effects of radiation, radiation detection instrumentation and calibration, external and internal dosimetry calculations, regulatory requirements (10 CFR Parts 19, 20, and 50 as applicable to RP technicians), and radiation protection program management — completing practice calculations and scenario questions after each domain; students solve dosimetry calculation problems by hand using standard formulas, then check work with instructor-provided solution keys.
  2. Using the NEI NUCP competency list as a checklist, each student self-rates current proficiency on every listed competency, then works through instructor-prepared scenario packets that require integrating knowledge across reactor operations, radiation protection, plant chemistry, and maintenance, reflecting the cross-disciplinary nature of the NUCP assessment; groups discuss correct responses and document lessons learned.
  3. Conduct a peer-teaching session in which each student selects one NRRPT or NUCP domain where they now feel confident and teaches a 10-minute mini-lesson to a small group using a whiteboard; listeners complete a five-question quiz on the taught material, and the teacher must achieve a class average of at least 75 percent to demonstrate mastery sufficient to instruct others.
NRRPT candidate handbook and content outline (available from nrrpt.org), NEI NUCP competency document, 10 CFR Parts 19, 20, and 50 excerpts, radiation protection textbook from Course 5, dosimetry calculation reference cards, scientific calculator, whiteboard and markersStudent scores at least 75 percent on domain practice question sets for all NRRPT domains and peer-teaching mini-lesson produces a group quiz average of at least 75 percent — both requirements must be met; instructor records results on the tracking spreadsheet
4Full-Length Mock Examinations and Final Remediation45practiceStudents complete full-length, timed mock examinations that replicate the format, length, and content weighting of each target credential, analyze performance reports to confirm readiness or complete final targeted remediation, and demonstrate sustained exam-taking stamina and strategy.
  1. Sit a full-length, closed-book, timed mock NRC written examination (non-licensed operator format) under examination conditions — no notes, timed strictly, answers recorded on an answer sheet — followed immediately by a scored debrief in which students mark every missed item on their domain tracker and spend a structured remediation period re-reading the relevant NUREG or textbook section before attempting a parallel question set on the same item types.
  2. Sit separate full-length timed mock examinations for the NRRPT (covering all six content domains in proportion to the published content outline) and a NUCP competency practice assessment; after each exam, complete an individual written error analysis identifying the root cause of each missed item as either a knowledge gap, a calculation error, a misread question, or a time-management failure, and record one corrective action for each root cause.
  3. Participate in an instructor-facilitated exam strategy workshop covering strategies specific to nuclear credentialing exams: reading technical specification and procedure-based questions, eliminating distractors on radiation calculation items, managing time across sections, and checking units and significant figures on dosimetry math; then sit a final abbreviated timed practice set drawn from previously missed items only, aiming for at least 80 percent accuracy to confirm remediation effectiveness.
Full-length mock examination booklets (NRC content-aligned, NRRPT content-aligned, NUCP-aligned), answer sheets, official-style timer, scientific calculator (same model allowed in actual exams), domain tracking spreadsheet, scratch paper, NUREG reference documents, NRRPT candidate handbookStudent must score at least 80 percent on the full-length NRC mock exam and at least 75 percent on the NRRPT mock exam (consistent with general NRRPT passing standards) to be certified as exam-ready by the instructor; any student below these thresholds receives a written remediation assignment and must complete a second mock session with documented improvement before course completion is awarded
Assessments
AssessmentTypeWeightPass standardMethod & rubric
Comprehensive Mock Certification Examination BatteryMock certification exam100%Minimum 80 percent on the NRC written exam mock; minimum 75 percent on the NRRPT mock; satisfactory (pass) on the NUCP competency mock and the OSHA 10 practice quiz; all four mock exams must be passed to receive a course completion certificateStudents sit a sequenced battery of four full-length, timed, closed-book mock examinations — NRC written (non-licensed operator format), NRRPT (all domains in published proportion), NUCP competency assessment, and OSHA 10 practice quiz — each administered under authentic examination conditions with no instructor assistance; scores are recorded on each student's cumulative domain tracking document, and the instructor certifies in writing that the student has demonstrated the knowledge and test-taking readiness required to sit the actual credentialing examinations.
Score · Time management
Program completion

External credential: NRC Non-Licensed Operator Prep; NRC Reactor Operator (RO) License (utility-sponsored); NRRPT Radiation Protection Tech; NUCP Uniform Curriculum (NEI); OSHA 10

Students prepare for and sit the NRC Non-Licensed Operator written qualification process, the NRC Reactor Operator license examination (administered through a utility-sponsored program under NRC oversight), the NRRPT certification examination, the NEI NUCP Uniform Curriculum assessment, and the OSHA 10 Outreach completion assessment, all conducted by their respective issuing bodies. Pass standard: Credential issued by the body.

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