🚧 Under construction — VoTechWorks is being built. A free tech program — complimentary, as our commitment to get America working.
voTechWorksGrade 13 · a vocational technology learning center, by urbanicity
newSchoolWorks.com › VoTechWorks › Building & Construction › Nuclear Power Plant Technician / Operator Prep › Certification Exam Preparation: NRC, NRRPT, NUCP, and OSHA Credentials › Lesson 2
BLD-NUCL84-11 · Lesson 2 · 60 clock hours · theory

Targeted Domain Review: NRC Written Exam and OSHA 10 Content

Objective. Students 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.

⚠ Pending professional review

This lesson, its worked examples and its practice questions 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.

VoTechWorks program approval and accreditation are still in progress. Credentials are issued only by the certifying bodies named in each program, after their own exams.

Why Targeted Domain Review Matters

You have spent months learning reactor physics, plant systems, radiological protection, and safety regulations. This lesson pulls those threads together with one goal in mind: performing well on the written examinations that lead to your credentials. The NRC Non-Licensed Operator and Reactor Operator written exams, the NRRPT examination, and the OSHA 10 assessment each test specific domains with specific weighting. Knowing which domains carry the most questions — and drilling those areas deliberately — is the most efficient path to a passing score.

NUREG-1021, Operator Licensing Examination Standards for Power Reactors, is the NRC's public guidance document that defines how written and operating tests are structured, what knowledge areas are sampled, and what passing standards apply. Review it as a map, not as reading material to memorize. It tells you which technical areas will appear and at roughly what depth.

NRC Written Exam Domain Review

Reactor Physics and Neutron Behavior. Understand the four-factor formula conceptually, the roles of delayed neutrons in making a reactor controllable, and why reactor period matters operationally. Know the difference between prompt criticality and delayed criticality, and why operators must never allow the former. Understand reactivity coefficients — moderator temperature coefficient, fuel temperature coefficient (Doppler), and void coefficient — and whether each is positive or negative in your reactor type, since a negative coefficient provides inherent safety feedback.

Reactor Coolant and Auxiliary Systems. Trace the flow path of primary coolant from reactor vessel through the steam generator (PWR) or directly to the turbine (BWR). Know the function of the pressurizer in a PWR — how heaters and spray maintain pressure — and what happens to reactor safety if pressure limits are exceeded. Understand the purpose of the Emergency Core Cooling System (ECCS), including high- and low-pressure injection trains, and the conditions that actuate them automatically.

Electrical Systems. Nuclear plants require multiple independent AC power trains and reliable DC power for instrumentation and control. Know how offsite power, onsite standby diesel generators, and station batteries relate to each other. A loss of offsite power (LOOP) event requires diesel generators to start and load automatically; delayed generator start is a reportable condition. Understand bus alignments and why certain loads are safety-related.

Instrumentation and Control Logic. Most reactor protection system (RPS) trips use two-out-of-four or two-out-of-three logic to balance reliability against spurious trips. Know what each common trip signal — high neutron flux, low coolant flow, high reactor coolant temperature, low pressure — protects against. Understand the difference between an analog protection channel and a digital logic channel, and why channel calibration and surveillance testing are required by technical specifications.

Radwaste Systems. Liquid, gaseous, and solid radioactive waste streams are processed separately. Know the general flow of each: liquid waste through demineralizers and evaporators, gaseous waste through delay beds or charcoal adsorbers, and solid waste packaged per NRC and DOT requirements. Effluent monitoring ensures releases remain within limits established in the plant's license.

Radiological Fundamentals. Review the three basic types of ionizing radiation — alpha, beta, and gamma — and the shielding material appropriate for each. Understand exposure, dose (rem or sievert), dose rate, and the ALARA principle (as low as reasonably achievable). Know how time, distance, and shielding work together to reduce dose. Understand what a declared pregnant worker's dose limit is versus the general occupational limit under 10 CFR Part 20, and know that limits are set by regulation, not by plant preference.

Technical Specifications (Tech Specs). Technical specifications are legally binding conditions of the operating license. Know the structure: Limiting Conditions for Operation (LCOs), Surveillance Requirements (SRs), and Action statements. When a system or component is found outside its LCO, the operator must enter the applicable Action and restore operability within the allowed outage time or take the specified compensatory action. Violating an Action statement is a reportable event. Practice reading LCO tables quickly, since the written exam tests this skill directly.

Emergency Operating Procedures (EOPs). EOPs are symptom-based procedures that direct operators to stabilize critical safety functions — reactivity control, reactor coolant inventory, reactor heat removal, radioactive release control, and containment integrity — regardless of the initiating event. Know the five or six critical safety functions used at most plants and understand that EOP entry is triggered by plant parameter thresholds, not by event identification.

OSHA 10 Domain Review

The OSHA 10 card certifies that you have completed ten hours of federally recognized safety training. The assessment covers key topics from 29 CFR 1910 (general industry) and 29 CFR 1926 (construction). For nuclear plant work, the most testable topics are:

Safety Emphasis

Lockout/tagout errors cause fatal accidents. In every practice scenario involving maintenance or equipment clearing, identify the energy source, isolate it, apply the lock, and verify zero energy before proceeding — no exceptions. ALARA is not optional in radiation work; it is a regulatory requirement under 10 CFR Part 20 and a professional habit you must build now.

Study Strategy for This Lesson

Complete each NRC domain review session and score your practice questions immediately. Record every missed item in your study notebook with the correct answer and a one-sentence explanation. Do not move on until you reach 75 percent in a domain; a second attempt on an alternate set is required if you fall short. For OSHA, treat the 40-question timed practice quiz as a dress rehearsal: closed book, timed, reviewed thoroughly afterward. Your instructor initials each passed domain on the tracking spreadsheet — that record is your evidence of readiness.

Key terms10

NUREG-1021The NRC document titled Operator Licensing Examination Standards for Power Reactors, which defines the structure, knowledge areas, and passing standards for NRC operator licensing examinations.
Limiting Condition for Operation (LCO)A technical specification requirement stating the minimum equipment or system capability that must be operable for a plant to operate at a given power level; failure to meet an LCO requires entry into the associated Action statement.
Reactivity CoefficientA measure of how reactor power or reactivity changes in response to a change in a plant parameter such as moderator temperature, fuel temperature, or coolant void fraction; a negative coefficient indicates inherent self-stabilizing behavior.
Two-out-of-Four LogicA reactor protection system voting arrangement in which at least two of four independent channels must detect an abnormal condition before a protective action, such as a reactor trip, is initiated, balancing reliability against spurious actuation.
Emergency Core Cooling System (ECCS)A set of safety systems designed to deliver cooling water to the reactor core following a loss-of-coolant accident or other event that threatens core coverage, typically including high-pressure and low-pressure injection trains.
ALARAAs Low As Reasonably Achievable — the regulatory principle, required by 10 CFR Part 20, that radiation doses to workers and the public must be kept as low as practicable using time, distance, and shielding controls.
Lockout/Tagout (LOTO)An OSHA-required energy control procedure in which hazardous energy sources are isolated, locked in the safe position, and verified at zero energy state before servicing or maintenance work begins on equipment.
Permit-Required Confined SpaceA confined space that contains or has the potential to contain a serious hazard, requiring an entry permit, atmospheric testing, an outside attendant, and a rescue plan before any worker may enter, per OSHA standards.
Critical Safety Function (CSF)One of the fundamental plant conditions — typically including reactivity control, reactor coolant inventory, core heat removal, and containment integrity — that Emergency Operating Procedures are designed to monitor and maintain.
Safety Data Sheet (SDS)A standardized 16-section document required under OSHA's Hazard Communication Standard that provides information on a chemical's hazards, safe handling, PPE requirements, and emergency response procedures.
In class: 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. · 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. · 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.
Materials: 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 spreadsheet
Check: Student 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

Practice check8

Answer each question, then check it. Nothing is recorded; this is your own practice.

NRC Non-Licensed Operator / Reactor Operator — Technical Specifications
1. A plant operator discovers that one of four channels in the reactor protection system is inoperable due to a failed sensor. The plant is operating at full power. According to technical specification Action statement requirements, the operator's immediate obligation is to:
NRC Non-Licensed Operator / Reactor Operator — Reactor Physics
2. Which type of reactivity coefficient is considered an inherent safety feature because it automatically reduces reactor power when fuel temperature rises?
NRC Non-Licensed Operator / Reactor Operator — Reactor Coolant System
3. In a pressurized water reactor, the primary purpose of the pressurizer is to:
NRC Non-Licensed Operator / Reactor Operator — Instrumentation and Control Logic
4. A reactor protection system uses two-out-of-three logic for a high-temperature trip. One channel fails in the tripped condition. How does the logic respond?
NRC Non-Licensed Operator / Reactor Operator — Radiological Fundamentals; NRRPT
5. Under the ALARA principle, which combination of actions most effectively reduces an operator's radiation dose during a task in a high-dose-rate area?
NRC Non-Licensed Operator / Reactor Operator — Emergency Operating Procedures
6. Which statement correctly describes the entry conditions for Emergency Operating Procedures at most commercial nuclear plants?
OSHA 10 — Lockout/Tagout
7. A maintenance technician is preparing to replace a pump motor that is fed by a 480-volt bus. Before beginning work, OSHA lockout/tagout requirements demand that the technician:
OSHA 10 — Confined Space Entry
8. When evaluating whether a space is a permit-required confined space under OSHA standards, which combination of characteristics triggers the permit requirement?
Record this lesson on my transcript. Sign in with your key and enrollment email to record lessons (enroll free if you have no key). This page stays open to read and practise.