NS RWM6 cheat sheet

The IAEA establishes international safety standards through the Fundamental Safety Principles (SF-1) and the GSR Part series; these are not directly binding but are adopted by member states into national law.

In the United States, the Atomic Energy Act of 1954, as amended, is the statutory basis for civilian and military nuclear regulation; the NRC implements it through 10 CFR Parts 20, 30, 40, 50, 60, 61, 70, 71, and 72.

Agreement States assume NRC authority over byproduct, source, and small quantities of special nuclear material under Section 274 of the Atomic Energy Act; NRC retains authority over fuel cycle facilities, federal facilities, and certain activities.

The Low-Level Radioactive Waste Policy Act of 1980 and its 1985 amendments made states responsible for disposing of low-level waste and allowed interstate compacts to restrict access to regional disposal facilities.

The Nuclear Waste Policy Act of 1982, as amended, assigns the U.S. Department of Energy responsibility for permanent disposal of spent nuclear fuel and high-level radioactive waste and authorized the Yucca Mountain project.

NRC license types include facility licenses (Part 50, 70, 72), materials licenses (Parts 30, 40, 70), transportation package certifications (Part 71), and disposal licenses (Part 61); each carries specific terms and conditions.

The NRC enforces compliance through notices of violation, civil penalties, and escalated enforcement; the five-level Enforcement Policy ranges from a Severity Level I (most significant) to Severity Level V (minor).

The Radiation Safety Officer (RSO) is the individual designated by a licensee to be responsible for implementing the radiation protection program; qualifications are specified in 10 CFR 20.1101 and applicable license conditions.

The three fundamental radiation protection principles are justification (no practice unless it produces sufficient benefit), optimization (ALARA), and dose limitation (individual doses do not exceed prescribed limits).

Occupational dose limits under 10 CFR 20.1201: total effective dose equivalent (TEDE) of 5 rem (50 mSv) per year; lens dose equivalent of 15 rem (150 mSv) per year; shallow dose equivalent to skin/extremities of 50 rem (500 mSv) per year.

General public dose limit under 10 CFR 20.1301: 100 mrem (1 mSv) TEDE per year and 2 mrem (0.02 mSv) in any one hour from external sources in unrestricted areas.

Dose equivalent is calculated as H = D × Q × N, where D is absorbed dose in rad or gray, Q is the quality factor (1 for beta/gamma, 20 for alpha), and N is the product of other modifying factors (usually 1).

ALARA programs require documented management commitment, dose goals below regulatory limits, periodic reviews of dose trends, and consideration of cost-benefit in selecting dose reduction measures.

The annual limit on intake (ALI) is the activity of a radionuclide that, if inhaled or ingested over a year, would result in a committed effective dose equivalent equal to the annual occupational limit.

Derived air concentration (DAC) is the concentration of a radionuclide in air that, if breathed for a working year (2,000 hours), would result in an intake equal to the ALI; DAC = ALI / (2,000 h × 1.2 m³/h).

Declared pregnant workers may voluntarily notify the licensee and, under 10 CFR 20.1208, receive a dose limit of 0.5 rem (5 mSv) to the embryo/fetus during the entire gestation period; the worker retains the right to revoke the declaration in writing.

The NRC classifies low-level radioactive waste as Class A, Class B, Class C, or Greater-Than-Class C (GTCC) based on concentration limits in 10 CFR 61.55 Tables 1 and 2; waste exceeding Class C limits is GTCC and generally not suitable for shallow land disposal.

Class A waste must meet the lowest concentration limits and generally requires no special stability; Class B and C waste require greater containment, and Class C waste must be stable and disposed of below the surface or with intruder barriers.

High-level radioactive waste (HLW) is defined in the Nuclear Waste Policy Act as spent nuclear fuel or the highly radioactive waste material resulting from reprocessing, which requires permanent isolation.

Transuranic (TRU) waste contains alpha-emitting transuranic nuclides with half-lives greater than 20 years and concentrations greater than 100 nCi/g (3,700 Bq/g) at the time of assay; in the U.S., defense TRU waste is disposed at the Waste Isolation Pilot Plant (WIPP).

Uranium mill tailings are regulated under the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978 and 40 CFR Part 192, which sets radon and radium concentration standards for disposal.

Waste characterization must identify radionuclide content, chemical and physical form, hazardous constituents, and dose rate; scaling factors (ratios of difficult-to-measure to easy-to-measure nuclides) are often used and must be technically defensible.

The waste classification process includes determination of the waste's radionuclide inventory, comparison to 10 CFR 61.55 limits, and consideration of the waste form and package stability requirements in 10 CFR 61.56.

Mixed waste contains both radioactive and hazardous chemical components and is regulated jointly by the NRC (or Agreement State) and EPA under the Resource Conservation and Recovery Act (RCRA).

Treatment methods include compaction, incineration, evaporation, ion exchange, precipitation, and solidification; the objective is volume reduction, hazard reduction, or conversion to a stable waste form.

Conditioning converts waste into a stable, leach-resistant form, typically by cementation, bituminization, or vitrification; the waste form must meet disposal facility waste acceptance criteria (WAC).

The waste form must satisfy 10 CFR 61.56 requirements for Class B and C waste, including structural stability, resistance to degradation, and minimal free liquids.

High-integrity containers (HICs) are used for Class B and C waste to provide containment during the institutional control period; they must meet specific structural and chemical durability criteria.

Segregation of waste by radionuclide content, dose rate, and chemical compatibility reduces handling hazards and prevents prohibited items (e.g., free liquids, explosives, pressurized containers) from entering disposal packages.

Dose rate limits for handling are controlled by time, distance, and shielding; remote handling tools and shielded transfer casks are used to keep worker doses ALARA.

Solidification of liquid waste typically uses Portland cement, which must be formulated to avoid free liquid, excessive heat generation, and chemical incompatibility with the waste.

Waste minimization includes source reduction, reuse, and recycling; the EPA hierarchy for waste management prioritizes source reduction over treatment and disposal.

Near-surface disposal facilities for low-level waste must meet performance objectives in 10 CFR 61.41 through 61.44: protection of the general population (25 mrem/yr), inadvertent intruder protection (500 mrem/yr), and protection of groundwater (4 mrem/yr to the aquifer).

The disposal facility design must include a liner system, leachate collection, and a low-permeability cover to limit water infiltration and radionuclide migration.

Waste acceptance criteria (WAC) specify the radionuclide limits, waste form, packaging, and documentation required for waste to be accepted at a disposal facility.

Storage of radioactive waste must provide adequate shielding, containment, criticality safety, and monitoring; storage areas are subject to security and access controls.

The institutional control period for a low-level waste disposal facility is typically 100 years, during which the licensee maintains the site and monitors performance.

Disposal facility operations include waste receipt inspection, package verification against WAC, emplacement, and recordkeeping; discrepancies must be resolved before waste acceptance.

Performance assessment (PA) is a systematic analysis of the long-term behavior of a disposal facility, including radionuclide release, transport, and dose to future populations.

Waste package tracking systems maintain records of package location, contents, and radionuclide inventory throughout storage and disposal.

Effluent concentration limits (ECLs) in 10 CFR 20, Appendix B, Table 2, restrict the concentration of radionuclides released to unrestricted areas; licensees must demonstrate compliance through effluent monitoring or calculations.

Environmental monitoring programs include air, water, soil, vegetation, and foodstuff sampling to verify that public doses are within limits and to detect unplanned releases.

The pathway analysis approach identifies the critical pathway by which radionuclides reach humans and calculates dose using exposure parameters such as inhalation rate, ingestion rate, and occupancy.

Effluent monitoring must be conducted at the point of release, and the results must be recorded and reported as required by 10 CFR 20.2103 and license conditions.

The lower limit of detection (LLD) for environmental samples should be below the applicable concentration limit to ensure that compliance can be demonstrated.

Airborne effluent monitoring includes continuous sampling with filters and charcoal cartridges to capture particulates and radioiodine; stack monitors are calibrated and tested for alarm function.

Liquid effluent monitoring includes sampling and analysis of discharged water; flow-proportional composite sampling is commonly used to account for varying discharge rates.

Environmental monitoring data must be compared to baseline or pre-operational data to distinguish facility contributions from background radiation.

Radioactive material packages are classified as Excepted, Industrial (Type 1, 2, or 3), Type A, Type B, or Type C, depending on the activity and the required level of containment and shielding.

Type B packages must withstand normal transport conditions and hypothetical accident conditions specified in 10 CFR 71.71 and 71.73, including a 9-meter drop, puncture, fire, and immersion tests.

The transport index (TI) is a dimensionless number that limits the radiation level at 1 meter from the package surface; it is used to control package accumulation and segregation during transport.

Surface radiation limits: for exclusive-use shipments, 10 mSv/h (1,000 mrem/h) at the package surface and 2 mSv/h (200 mrem/h) at 1 meter; for non-exclusive use, 2 mSv/h at the surface and 0.1 mSv/h (10 mrem/h) at 1 meter.

Package marking and labeling requirements include the proper shipping name, UN number, radionuclide, activity, and transport index; labels are Category I (White), II (Yellow), or III (Yellow).

Shipping papers must include the radionuclide, activity, physical and chemical form, package type, and transport index, and must be readily accessible during transport.

The consignor is responsible for package preparation, marking, labeling, and documentation; the carrier is responsible for placarding and safe transport.

In the U.S., transportation of radioactive material is regulated by the NRC (10 CFR Part 71) and the Department of Transportation (49 CFR Parts 171-180), with modal-specific requirements from PHMSA.

Emergency planning zones (EPZs) for nuclear power plants include a plume exposure pathway EPZ of about 10 miles (16 km) and an ingestion pathway EPZ of about 50 miles (80 km).

Emergency action levels (EALs) are predefined, observable criteria used to initiate emergency response actions; they are categorized as Notification of Unusual Event, Alert, Site Area Emergency, and General Emergency.

The incident command system (ICS) provides a standardized organizational structure for emergency response, including command, operations, planning, logistics, and finance/administration sections.

Protective action guides (PAGs) are dose projections that warrant protective actions such as sheltering, evacuation, or administration of stable iodine; EPA PAGs are commonly used for planning.

Emergency response drills and exercises must be conducted periodically; NRC licensees typically conduct biennial exercises evaluated by the NRC and FEMA.

Radiological assessment during an emergency includes plume modeling, environmental sampling, and dose rate surveys to characterize the release and guide protective actions.

Notification requirements: licensees must notify the NRC Operations Center within 15 minutes of discovery of an event that may require emergency response, and must make notifications to state and local authorities as specified in the emergency plan.

Recovery and reentry planning includes dose assessment, decontamination, and criteria for unrestricted use of affected areas.

A quality assurance (QA) program must be established for activities affecting the safety of radioactive waste management, including design, construction, operation, and decommissioning, in accordance with 10 CFR 50, Appendix B, or equivalent criteria.

The QA program includes documented procedures, design control, procurement control, inspection, testing, and corrective action to ensure that items and services meet specified requirements.

Records retention requirements vary by license condition and regulation; generally, records of waste disposal, environmental monitoring, and personnel dosimetry must be retained for the life of the license and beyond.

The records management system must ensure that records are legible, identifiable, retrievable, and protected from damage or loss; electronic records must be backed up and controlled.

Audits and surveillance are planned and periodic evaluations of the QA program and operational activities to verify compliance and identify deficiencies.

Nonconformance and corrective action processes ensure that deficiencies are documented, evaluated, and corrected, and that the effectiveness of corrective actions is verified.

Training records must document that personnel have the required qualifications and have received radiation safety, emergency response, and job-specific training.

The waste acceptance documentation includes a certificate of compliance or waste profile, which records the waste characteristics and confirms that the waste meets the facility WAC.