NBR ARO Exam cheat sheet

The Atomic Energy Act of 1954, as amended, is the statutory basis for NRC authority over byproduct, source, and special nuclear material; agreement states derive authority from Section 274.

10 CFR Part 20 sets radiation protection standards: 1 mSv (100 mrem) annual TEDE limit for individual members of the public from licensed operations.

10 CFR Part 30 governs byproduct material; Part 31 covers general licenses; Part 32 covers specific license issuance for byproduct material.

Occupational dose limits under Part 20: 50 mSv (5 rem) annual TEDE; lens of eye 150 mSv (15 rem); extremities and skin 500 mSv (50 rem).

ALARA is codified in 10 CFR 20.1101(b): licensees must use procedures and engineering controls based on sound radiation protection principles.

Declared pregnant workers may voluntarily submit Form NRC-3; dose to the embryo/fetus is limited to 5 mSv (0.5 rem) over the gestation period.

Agreement states regulate most byproduct material under state law; NRC retains authority over federal facilities and certain categories such as greater-than-class-C waste.

A specific license application must include proposed radionuclides, quantities, purpose, facility description, radiation safety officer designation, and training/experience of users.

General licenses (e.g., 10 CFR 31.5) require no application but impose possession limits and labeling, transfer, and reporting conditions.

Amendments require submission of revised pages and a description of the change; certain amendments qualify for expedited review under 10 CFR 2.109.

Renewal applications must be filed at least 30 days before expiration for byproduct material licenses under 10 CFR 30.37 to avoid lapse.

Reciprocity under 10 CFR 150.20 allows out-of-state licensees to work in agreement states for up to 180 days per year upon filing NRC Form 241.

Termination requires decommissioning and confirmation surveys demonstrating residual radioactivity meets the release criteria of 10 CFR 20 Subpart E.

Financial assurance for decommissioning is required when licensed quantities exceed thresholds in 10 CFR 30.35, using a formula based on radionuclide-specific cost factors.

Dose equivalent H = absorbed dose D × radiation weighting factor wR; effective dose sums tissue doses × tissue weighting factors wT (ICRP 103/26).

Inverse square law: dose rate varies as 1/r²; doubling distance from a point source reduces exposure rate to one quarter.

Half-value layer (HVL) = 0.693/μ; after n half-value layers, transmitted intensity = I₀ × (1/2)^n.

External exposure controls follow time, distance, and shielding; internal exposure controls follow containment, ventilation, and contamination control.

Annual limit on intake (ALI) and derived air concentration (DAC) convert intake to committed effective dose; DAC = ALI divided by 2.4 × 10⁹ mL of air breathed per year.

Survey instruments must be calibrated at intervals not exceeding 12 months and after repair, per 10 CFR 20.1501 and license conditions.

Personnel monitoring is required when an individual is likely to receive 10 percent or more of an annual occupational dose limit (10 CFR 20.1502).

Sealed sources must be tested for leakage at intervals not exceeding 6 months for beta/gamma sources and 3 months for alpha sources, per license conditions and 10 CFR 30.53.

Storage areas must be posted with the radiation symbol and appropriate caution signs per 10 CFR 20.1902; containers must be labeled with radionuclide, activity, and date.

Security requirements under 10 CFR 37 apply to category 1 and 2 quantities of radioactive material: access controls, background checks, and physical protection.

Dosimetry processors must be accredited; badges are exchanged at intervals not exceeding one calendar quarter unless otherwise specified.

Area surveys must be documented and instruments must be operable and within calibration; unusable instruments are removed from service.

Inventory records for sealed sources must be maintained and reconciled at intervals specified in the license, typically every 6 months.

NRC inspectors conduct announced and unannounced inspections; licensees must permit access to facilities and records under Section 161 of the Atomic Energy Act.

Violations are categorized by severity; a Severity Level I is the most significant and may involve willful misconduct or actual safety consequence.

Enforcement options include notices of violation, civil penalties, orders, and license modification, suspension, or revocation.

Civil penalties for most Part 30 violations are adjusted annually for inflation; each day of a continuing violation may be a separate violation.

Licensees may request an alternative dispute resolution (ADR) or a pre-decisional enforcement conference before an order becomes effective.

A notice of violation is not a final agency action; licensees may respond in writing within the time specified, typically 30 days.

Willful violations may be referred for criminal prosecution under 18 U.S.C. Section 1001 or Section 223 of the Atomic Energy Act.

Personnel exposure records must be preserved for the life of the individual, and maintained for at least 30 years after termination of employment or license, per 10 CFR 20.2106.

Dose records must be reported to the individual annually and upon termination of employment; the individual may request a report of cumulative dose.

Immediate notification is required for theft or loss of licensed material, or overexposure exceeding limits, using the NRC Operations Center.

A written report to the NRC is required within 30 days for events such as theft or loss of licensed material, or a dose exceeding the annual limit.

Records of surveys, calibrations, and instrument checks must be retained for at least 3 years unless otherwise specified by license condition.

Licensees must retain records of receipt, transfer, and disposal of licensed material for at least 3 years, and longer for certain sources.

Annual reports to the NRC are required for certain byproduct material licenses, such as those issued under 10 CFR 32 or for sealed sources under 10 CFR 30.36.

The radiation safety officer is responsible for implementing the radiation protection program, training, audits, and ensuring compliance with license conditions.

Licensees must provide training to workers before they work with licensed material, covering health risks, precautions, and applicable regulations.

The RSO must have sufficient authority, organizational independence, and resources to implement the radiation protection program effectively.

Licensees must not permit an individual to act as a radiation worker without instruction in the hazards and precautions, per 10 CFR 19.12.

Audits of the radiation protection program must be conducted at intervals specified in the license, commonly annually, and documented.

A licensee must notify the NRC of changes in the RSO or other key personnel within the time specified in the license, often 30 days.

Ethical obligations include accurate reporting of dosimetry, honest documentation of surveys, and prompt disclosure of safety issues.