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Building an ALARA Program for a Medical Facility

Troy Zhou, PhD, DABR, DABSNM By Troy Zhou, PhD, DABR, DABSNM
December 16, 2025 16 min read

An ALARA program is the documented system that turns 'as low as reasonably achievable' from a slogan into verifiable practice — with management commitment, dose constraints, investigational levels, time-distance-shielding controls, monitoring, training, and periodic review. Done well, it keeps occupational and public doses well below regulatory limits and demonstrates a defensible radiation-protection culture to the NRC or Agreement State.123

ALARA is one of the most quoted and least operationalized phrases in radiation safety. Many facilities can recite "as low as reasonably achievable" but cannot point to the written program, the investigational levels, or the review records that prove they are actually achieving it. This guide explains what an ALARA program contains, how the underlying physics of dose control works, what the regulatory framework requires, and how to build a program that both satisfies inspectors and genuinely reduces dose. DRPS supports this work through its radiation safety officer consulting and medical physicist consulting services across Florida, Maryland, Virginia, Washington DC, California, and Nevada.

Introduction

ALARA is a formal radiation-protection principle defined in NRC regulations: making every reasonable effort to keep radiation exposures as far below the dose limits as practical, consistent with the purpose of the licensed activity. It explicitly accounts for the state of technology, the economics of improvements relative to benefit, and the broader public-health context.1

The crucial word is reasonably. ALARA does not mean zero dose, and it does not require spending unlimited resources to shave off a microsievert. It means a deliberate, documented optimization: identifying where dose comes from, applying controls that are reasonable given the technology and cost, and verifying through monitoring that the controls work. A program that only displays a poster is not an ALARA program; a program that defines constraints, measures performance against them, and acts on deviations is.

This article covers the regulatory definition, the dose limits ALARA operates beneath, the physics of time-distance-shielding, investigational levels, the program elements the NRC expects, the role of the RSO and committee, and practical steps to build and sustain an effective program. For the broader licensing context, see our NRC license guide and the Radiation Safety Officer role.

Topic Explanation

What is an ALARA program?

An ALARA program is the written set of policies, responsibilities, controls, and review processes a licensee uses to keep doses as low as reasonably achievable. It is broader than dose limits: limits are the legal ceiling, while ALARA is the continuous effort to stay well beneath that ceiling.

A functioning program answers a series of questions:

  • Has management made a written, visible commitment to ALARA?
  • Who is responsible — the RSO, the committee, the physicists, the workers?
  • What are the facility's dose constraints and investigational levels?
  • What engineering controls, work practices, and shielding are in place?
  • How are doses monitored, recorded, and trended?
  • What happens when an investigational level is exceeded?
  • How often is the program reviewed, and by whom?

These elements come straight from NRC operating-philosophy guidance and are what an inspector looks for. For how monitoring feeds the program, see occupational exposure monitoring.

ALARA versus dose limits

It is essential to distinguish the two. Dose limits are regulatory maximums; ALARA is the optimization below them. Under 10 CFR Part 20, the principal occupational and public limits include:1

  • Occupational total effective dose equivalent: 50 mSv (5 rem) per year.
  • Public dose from the licensed operation: 1 mSv (0.1 rem) per year.
  • Declared-pregnant-worker dose to the embryo/fetus: 5 mSv (0.5 rem) over the pregnancy, with effort to avoid substantial variation above a uniform rate.

A facility can be fully compliant with these limits and still have a weak ALARA program if it makes no effort to drive doses lower where reasonable. ALARA is what fills the gap between "legal" and "as low as reasonably achievable." For the pregnant-worker specifics, see the pregnant radiation worker.

Key Technical Principles

The three external-dose controls: time, distance, shielding

External dose control rests on three physical levers. Dose accumulates in proportion to time spent near a source, falls with the square of distance, and is reduced exponentially by shielding.

Time is linear — halving the time near a source halves the dose:

Distance follows the inverse-square law for a point source, which is often the single most powerful control:

Doubling the distance cuts the dose rate to one-quarter. Shielding attenuates the beam exponentially, conveniently expressed with half-value layers (HVL) or tenth-value layers (TVL):

Worked example: combining the controls

Suppose an unshielded task produces a dose rate of at m, and the task takes 30 minutes. The unmitigated dose is:

Now apply ALARA controls: move the worker to m (double the distance), cut the task time to 15 minutes through better preparation, and add 1 HVL of shielding. The combined factor is:

The same task now delivers about 1/16 of the original dose — and notice that distance and time alone accounted for a factor of 8 before any shielding was added. This is the core ALARA insight: reasonable changes to work practice often beat adding lead.

Investigational levels

A mature ALARA program uses investigational levels — administrative thresholds set well below the regulatory limit that trigger review when crossed. A common two-tier structure is illustrated below.

Element Regulatory limit (annual) Typical ALARA Level I (review) Typical ALARA Level II (investigate/act) Action
Occupational TEDE 50 mSv ~5 mSv (10% of limit) ~15 mSv (30% of limit) RSO review of cause; corrective action and documentation at Level II
Public dose 1 mSv Set by program well below 1 mSv Set by program Evaluate controls and adjacent occupancy
Declared pregnant worker (fetus) 5 mSv/gestation Monthly tracking against uniform rate Approaching constraint Reassign/shield; counsel worker

The specific investigational values are facility-defined and should be documented in the program; the percentages above are common illustrative choices, not regulatory mandates. The point of the two tiers is early detection: Level I prompts a look, Level II prompts documented corrective action — long before any worker approaches the legal limit.23

Clinical Impact

A strong ALARA program protects staff, supports recruitment and retention, and reduces regulatory risk. Its effects show up in several ways:

  • Lower occupational doses. Interventional, nuclear medicine, and fluoroscopy staff are the highest-dose groups in most facilities; ALARA controls (distance, shielding, dosimetry feedback) measurably reduce their exposure.
  • Defensible inspections. Documented constraints, trended dose records, and investigational-level reviews are exactly what NRC and Agreement State inspectors expect to see. Missing ALARA documentation is a recurrent finding — see common radiation safety violations and how to avoid them.
  • A genuine safety culture. When workers see that exceedances are reviewed and acted on (not punished reflexively), they engage with the program, which is the strongest dose-reduction tool of all.
  • Cross-disciplinary benefit. Even guidance on induced radioactivity in high-energy radiotherapy frames its recommendations explicitly "in the spirit of ALARA," reflecting how pervasive the principle is across medical physics.6

Practical Optimization Tips

1. Start with a written management commitment

ALARA begins at the top. A short, signed management policy statement establishing the commitment to ALARA is both a regulatory expectation and the cultural foundation for everything else.2

2. Define dose constraints and investigational levels

Set Level I and Level II investigational levels for occupational and public dose, document them, and make sure the RSO and workers know what triggers a review. Tie them to the monitoring period so they are actually checked.

3. Apply the hierarchy of controls

Favor engineering controls and good work practices over relying solely on personal protective equipment. Optimize time (preparation and training), distance (tools, room layout, remote handling), and shielding (barriers, syringe and vial shields, mobile shields). For instrument selection, see choosing the right radiation survey meter.

4. Monitor, record, and trend

Issue and read dosimeters on schedule, record results, and trend them. Trending — not just comparing to limits — is what reveals a rising exposure before it becomes a problem. Contamination surveys and decontamination practices support the same goal; see nuclear medicine decontamination best practices.

5. Train and re-train

Initial and refresher training on ALARA, dose controls, and procedures is required and effective. Make it specific to the actual tasks workers perform.

6. Review and close the loop

Review dose records each period, investigate exceedances, document corrective actions, and conduct an annual program review. The audit trail is what makes the program defensible.

Common pitfalls to avoid

  • Poster-only ALARA. A wall sign is not a program; inspectors look for written constraints, records, and reviews.
  • No investigational levels. Without administrative thresholds, there is no early-warning system below the legal limit.
  • Ignoring trends. Comparing only to the annual limit misses gradual increases that are easy to correct early.
  • Punitive responses. Treating an exceedance review as discipline discourages reporting and undermines the culture.
  • Reaching for shielding first. Distance and time are often cheaper and more effective; optimize the whole hierarchy.
  • Skipping the annual review. A program that is never re-examined drifts out of step with actual practice.

Regulatory Considerations

An ALARA program must align with NRC 10 CFR Part 20 and the recognized NRC operating-philosophy and program guidance, or the equivalent Agreement State requirements. The controlling and guidance documents include:

  • 10 CFR Part 20 — Standards for Protection Against Radiation. Defines ALARA, sets occupational and public dose limits, and requires the radiation protection program to use procedures and engineering controls to achieve doses ALARA.1
  • NRC Regulatory Guide 8.10 — Operating Philosophy for Maintaining Occupational Radiation Exposures As Low As Is Reasonably Achievable. Describes the management commitment, responsibilities, and program elements for an effective ALARA program.2
  • NRC Regulatory Guide 8.13 — Instruction Concerning Prenatal Radiation Exposure and related guidance, relevant to the declared-pregnant-worker constraint within ALARA.4
  • NRC Regulatory Guide 8.18 — Information Relevant to Ensuring That Occupational Radiation Exposures at Medical Institutions Will Be As Low As Reasonably Achievable. Provides medical-facility-specific ALARA guidance, including investigational levels.3
  • NRC NUREG-1556, Volume 9 — Program-Specific Guidance About Medical Use Licenses. Sets expectations for the radiation protection program, including ALARA, for medical-use licensees.5
  • ICRP Publication 103. Frames the international system of radiological protection around justification, optimization (the international expression of ALARA), and dose limitation.7

Jurisdiction note: ALARA under 10 CFR Part 20 applies to byproduct material regulated by the NRC or an Agreement State. In DRPS's footprint, Florida, Maryland, Virginia, California, and Nevada are Agreement States that administer their own equivalent radiation-control rules, while Washington, DC is regulated directly by the NRC. X-ray-producing machines are regulated separately by the FDA and the states, but the ALARA culture applies across the whole facility. A licensee must confirm which authority and which exact requirements apply. For inspection preparation, see preparing for an NRC inspection.

Frequently Asked Questions (FAQs)

What does ALARA mean?

ALARA stands for "as low as reasonably achievable." It is the principle that radiation doses to workers and the public should be kept as far below regulatory limits as is reasonably achievable, taking into account the state of technology, the economics of improvements, and the benefits to public health and safety.

Is ALARA a regulatory requirement or just a goal?

Both. ALARA is defined and required as a radiation protection principle under NRC 10 CFR Part 20, and licensees are expected to develop, document, and implement an ALARA program. NRC Regulatory Guide 8.10 provides guidance on operating philosophy and program elements.

What are investigational levels in an ALARA program?

Investigational levels are administrative dose values, set well below regulatory limits, that trigger review and action when exceeded. They are typically defined in two tiers (Level I and Level II) and let a facility detect and correct rising exposures long before a worker approaches a legal limit.

How is ALARA actually achieved day to day?

Primarily through the three classic external-dose controls — minimizing time near sources, maximizing distance, and using shielding — combined with engineering controls, good work practices, contamination control, monitoring, and training. The program documents these controls and verifies they are working.

Who is responsible for the ALARA program?

Management commitment is the foundation, but day-to-day responsibility usually rests with the Radiation Safety Officer (RSO), supported by a Radiation Safety Committee where required, qualified medical physicists, and every worker who uses radiation. ALARA is a shared responsibility with clearly defined roles.

How often should an ALARA program be reviewed?

Dose records and investigational-level exceedances should be reviewed regularly (for example, at each monitoring period), and the overall program should be reviewed at least annually, plus whenever practices, equipment, workload, or staffing change materially.

Does ALARA apply to patients?

ALARA as a regulatory term under 10 CFR Part 20 applies to occupational and public dose. Patient dose is managed under separate principles such as justification and optimization, but the same culture of dose awareness supports both. Medical-event reporting and patient-dose optimization are handled under other parts of the program.

Key Takeaways

  • ALARA is a required, documented principle — not a slogan. It is defined in 10 CFR Part 20 and expected to be implemented as a real program.
  • Limits are the ceiling; ALARA is the optimization below it. A facility can be compliant yet still have a weak ALARA effort.
  • Time, distance, and shielding are the core levers. Distance (inverse-square) and time are often the cheapest and most effective.
  • Investigational levels create early warning. Two-tier administrative thresholds catch rising doses long before the legal limit.
  • Monitor, trend, and review. Records, trends, exceedance reviews, and an annual program review make the program effective and defensible.
  • Align with NRC/Agreement State guidance. RG 8.10, RG 8.18, NUREG-1556, and 10 CFR Part 20 define what inspectors expect.

Conclusion

A good ALARA program is the difference between saying "as low as reasonably achievable" and proving it. The physics is simple — time, distance, and shielding — but the program is what makes those controls systematic: a written management commitment, defined dose constraints and investigational levels, layered controls, monitoring and trending, training, and periodic review with a documented audit trail. Facilities that build ALARA as a living program rather than a wall poster protect their staff, strengthen their safety culture, and stand on solid ground during NRC or Agreement State inspection.

How DRPS Can Help

Diagnostic Radiation Physics Services (DRPS) helps medical facilities design and operate ALARA programs that satisfy regulators and actually reduce dose. This includes radiation safety officer consulting, ALARA program and investigational-level development, dose-record review and trending, shielding and work-practice optimization, staff training support, and medical physicist consulting aligned with NRC and Agreement State requirements.

DRPS serves facilities across our service locations, including Florida, Maryland, Virginia, Washington DC, California, and Nevada. For licensing support, see our radioactive material license support.

Related Resources

References

  1. U.S. Nuclear Regulatory Commission. 10 CFR Part 20: Standards for Protection Against Radiation (see §20.1003 definition of ALARA and §20.1101 radiation protection programs). ecfr.gov
  2. U.S. Nuclear Regulatory Commission. Regulatory Guide 8.10: Operating Philosophy for Maintaining Occupational Radiation Exposures As Low As Is Reasonably Achievable. nrc.gov
  3. U.S. Nuclear Regulatory Commission. Regulatory Guide 8.18: Information Relevant to Ensuring That Occupational Radiation Exposures at Medical Institutions Will Be As Low As Reasonably Achievable. nrc.gov
  4. U.S. Nuclear Regulatory Commission. Regulatory Guide 8.13: Instruction Concerning Prenatal Radiation Exposure. nrc.gov
  5. U.S. Nuclear Regulatory Commission. NUREG-1556, Volume 9, Revision 3: Program-Specific Guidance About Medical Use Licenses. nrc.gov
  6. Thomadsen B, Nath R, Bateman FB, et al. Potential hazard due to induced radioactivity secondary to radiotherapy: the report of Task Group 136 of the American Association of Physicists in Medicine. Health Physics. 2014;107(5):442-460. doi:10.1097/HP.0000000000000139. doi.org
  7. International Commission on Radiological Protection. ICRP Publication 103: The 2007 Recommendations of the International Commission on Radiological Protection. Annals of the ICRP. 2007;37(2-4). icrp.org
  8. National Council on Radiation Protection and Measurements. Implementation of the Principle of As Low As Reasonably Achievable (ALARA) for Medical and Dental Personnel. NCRP Report No. 107. Bethesda, MD: NCRP; 1990. ncrponline.org
  9. National Council on Radiation Protection and Measurements. Limitation of Exposure to Ionizing Radiation. NCRP Report No. 116. Bethesda, MD: NCRP; 1993. ncrponline.org
  10. U.S. Nuclear Regulatory Commission. Occupational Dose Limits (10 CFR 20.1201) and Dose to Individual Members of the Public (10 CFR 20.1301). nrc.gov