PERMANENT RULES
Date of Adoption: March 15, 2000.
Purpose: These regulations significantly update requirements for industrial radiographic operations (chapter 246-243 WAC and WAC 246-235-084), clarify the requirements for determining prior occupational dose (WAC 246-221-020), break up a long section into three smaller sections (WAC 246-235-080, 246-235-084, and 246-235-086), and correct cross referencing all to bring radiation protection regulations into conformance with the United States Nuclear Regulatory Commission rules.
Citation of Existing Rules Affected by this Order: Repealing WAC 246-243-210; and amending WAC 246-220-007, 246-220-010, 246-221-020, 246-235-080, 246-235-090, 246-243-020, 246-243-030, 246-243-050, 246-243-060, 246-243-080, 246-243-090, 246-243-100, 246-243-110, 246-243-120, 246-243-130, 246-243-140, 246-243-150, 246-243-160, 246-243-170, 246-243-180, 246-243-190, 246-243-195, 246-243-200, 246-243-220, 246-243-230, 246-254-150, 246-252-001, and 246-252-030.
Statutory Authority for Adoption: RCW 70.98.050.
Adopted under notice filed as WSR 00-04-088 on February 2, 2000.
Number of Sections Adopted in Order to Comply with Federal Statute: New 0, Amended 0, Repealed 0; Federal Rules or Standards: New 8, Amended 28, Repealed 1; or Recently Enacted State Statutes: New 0, Amended 0, Repealed 0.
Number of Sections Adopted at Request of a Nongovernmental Entity: New 0, Amended 0, Repealed 0.
Number of Sections Adopted on the Agency's Own Initiative: New 0, Amended 0, Repealed 0.
Number of Sections Adopted in Order to Clarify, Streamline, or Reform Agency Procedures: New 0, Amended 0, Repealed 0.
Number of Sections Adopted Using Negotiated Rule Making: New 0, Amended 0, Repealed 0; Pilot Rule Making: New 0, Amended 0, Repealed 0; or Other Alternative Rule Making: New 8, Amended 28, Repealed 1. Effective Date of Rule: Thirty-one days after filing.
March 23, 2000
M. C. Selecky
Secretary
OTS-3595.2
AMENDATORY SECTION(Amending Order 208, filed 10/29/91, effective
11/29/91)
WAC 246-254-150
Fees for perpetual care and maintenance.
(1) Persons with licenses specifically authorizing the receipt, possession, or use of natural uranium and its decay daughters for the extraction of uranium or thorium compounds or for the reclamation and disposal of the associated tailings or waste shall:
(a) Make quarterly payments of twenty cents per kilogram of uranium or thorium compound milled out of the raw ore;
(b) Remit this payment within thirty days after the end of each calendar quarter; and
(c) Pay to the department a minimum of two hundred fifty thousand dollars (1978 dollars) to cover the costs of long-term surveillance prior to the termination of a uranium or thorium mill license.
(2) Licensees under this section may make additional
payments to meet the minimum, prior to the release of any surety
arranged by the licensee in accordance with WAC ((246-235-080
(6)(d))) 246-235-086(4).
[Statutory Authority: RCW 43.70.110. 91-22-027 (Order 208), § 246-254-150, filed 10/29/91, effective 11/29/91. Statutory Authority: RCW 43.70.040. 91-02-049 (Order 121), recodified as § 246-254-150, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. 87-01-031 (Order 2450), § 402-70-080, filed 12/11/86.]
OTS-3596.2
AMENDATORY SECTION(Amending Order 187, filed 8/7/91, effective
9/7/91)
WAC 246-252-001
Reclamation and decommissioning.
A
specific plan for reclamation and disposal of tailings and for
decommissioning the site of uranium or thorium milling operations
shall be included as part of the proposed action assessed under
SEPA regulations and guidelines as required by WAC ((246-235-080
(6)(a))) 246-235-086(1) for licensing of environmentally
significant operations. For any uranium or thorium mill in
operation on or before the effective date of this regulation for
which a plan for reclamation and disposal of tailings and
decommissioning of the site has not been submitted and assessed,
such a plan must be submitted to the department and a final
environmental impact statement or final declaration of
nonsignificance must accompany or precede the license renewal.
[Statutory Authority: RCW 70.98.050 and 70.98.080. 91-16-109 (Order 187), § 246-252-001, filed 8/7/91, effective 9/7/91. Statutory Authority: RCW 43.70.040. 91-02-049 (Order 121), recodified as § 246-252-001, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. 79-12-073 (Order 1459), § 402-52-005, filed 11/30/79, effective 1/1/80.]
As used in this section, the term "as low as reasonably achievable" has the same meaning as in WAC 246-220-007. The term by-product material means the tailings or wastes produced by the extraction or concentration of uranium or thorium from any ore processed primarily for its source material content.
As required by WAC 246-235-110(6), each applicant for a license to possess and use source material in conjunction with uranium or thorium milling, or by-product material at sites formerly associated with such milling, is required to include in a license application proposed specifications relating to the milling operation and the disposition of tailings or waste resulting from such milling activities. This section establishes criteria relating to the siting, operation, decontamination, decommissioning, and reclamation of mills and tailings or waste systems and sites at which such mills and systems are located and site and by-product material ownership. Applications must clearly demonstrate how these criteria have been addressed. The specifications shall be developed considering the expected full capacity of tailings or waste systems and the lifetime of mill operations. Where later expansions of systems or operations may be likely, the amenability of the disposal system to accommodate increased capacities without degradation in long-term stability and other performance factors shall be evaluated.
Licensees or applicants may propose alternatives to the specific requirements in these criteria. The alternative proposals may take into account local or regional conditions, including geology, topography, hydrology, and meteorology. The department may find that the proposed alternatives meet the department's requirements if the alternatives will achieve a level of stabilization and containment of the sites concerned, and a level of protection for public health, safety, and the environment from radiological and nonradiological hazards associated with the sites, which is equivalent to, to the extent practicable, or more stringent than the level which would be achieved by the requirements of the standards promulgated by the United States Environmental Protection Agency in 40 CFR 192, Subparts D and E.
(1) Criterion 1 - In selecting among alternative tailings disposal sites or judging the adequacy of existing tailings sites, the following site features which would contribute to meeting the broad objective of permanent isolation of the tailings and associated contaminants from man and the environment for one thousand years to the extent reasonably achievable, and in any case, for at least two hundred years without ongoing active maintenance shall be considered:
(a) Remoteness from populated areas;
(b) Hydrogeologic and other environmental conditions conducive to continued immobilization and isolation of contaminants from groundwater sources; and
(c) Potential for minimizing erosion, disturbance, and dispersion by natural forces over the long term.
The site selection process must be an optimization to the maximum extent reasonably achievable in terms of these features.
In the selection of disposal sites, primary emphasis shall be given to isolation of tailings or wastes, a matter having long-term impacts, as opposed to consideration only of short-term convenience or benefits, such as minimization of transportation or land acquisition costs. While isolation of tailings will be a function of both site characteristics and engineering design, overriding consideration shall be given to siting features given the long-term nature of the tailings hazards.
Tailings shall be disposed in a manner such that no active maintenance is required to preserve the condition of the site.
(2) Criterion 2 - To avoid proliferation of small waste disposal sites, by-product material from in-situ extraction operations, such as residues from solution evaporation or contaminated control processes, and wastes from small remote above ground extraction operations shall be disposed at existing large mill tailings disposal sites; unless, considering the nature of the wastes, such as their volume and specific activity and the costs and environmental impacts of transporting the wastes to a large disposal site, such offsite disposal is demonstrated to be impracticable or the advantage of onsite burial clearly outweighs the benefits of reducing the perpetual surveillance obligations.
(3) Criterion 3 - The "prime option" for disposal of tailings is placement below grade, either in mines or specially excavated pits (that is, where the need for any specially constructed retention structure is eliminated).
The evaluation of alternative sites and disposal methods performed by mill operators in support of their proposed tailings disposal program (provided in applicants' environmental reports) shall reflect serious consideration of this disposal mode. In some instances, below grade disposal may not be the most environmentally sound approach, such as might be the case if a groundwater formation is relatively close to the surface or not very well isolated by overlying soils and rock. Also, geologic and topographic conditions might make full, below grade burial impracticable; for example, near-surface bedrock could create prominent excavation costs while more suitable alternate sites may be available. Where full below grade burial is not practicable, the size of the retention structures, and the size and steepness of slopes of associated exposed embankments, shall be minimized by excavation to the maximum extent reasonably achievable or appropriate, given the geologic and hydrogeologic conditions at a site. In these cases, it must be demonstrated that an above-grade disposal program will provide reasonably equivalent isolation of the tailings from natural erosional forces.
(4) Criterion 4 - The following site and design criteria shall be adhered to whether tailings or wastes are disposed of above or below grade:
(a) Upstream rainfall catchment areas must be minimized to decrease erosion potential and the size of the probable maximum flood which could erode or wash out sections of the tailings disposal area.
(b) Topographic features shall provide good wind protection.
(c) Embankment and cover slopes shall be relatively flat after final stabilization to minimize erosion potential and to provide conservative factors of safety assuring long-term stability. The broad objective should be to contour final slopes to grades which are as close as possible to those which would be provided if tailings were disposed of below grade; this could, for example, lead to slopes of about ten horizontal to one vertical (10h:1v) or less steep. In general, slopes should not be steeper than about 5h:1v. Where steeper slopes are proposed, reasons why a slope less steep than 5h:1v would be impracticable should be provided, and compensating factors and conditions which make such slopes acceptable should be identified.
(d) A fully self-sustaining vegetative cover shall be established or rock cover employed to reduce wind and water erosion to negligible levels.
Where a full vegetative cover is not likely to be self-sustaining due to climatic conditions, such as in semi-arid and arid regions, rock cover shall be employed on slopes of the impoundment system. The NRC will consider relaxing this requirement for extremely gentle slopes such as those which may exist on the top of the pile.
The following factors shall be considered in establishing the final rock cover design to avoid displacement of rock particles by human and animal traffic or by natural processes, and to preclude undercutting and piping:
(i) Shape, size, composition, gradation of rock particles (excepting bedding material, average particle size shall be at least cobble size or greater);
(ii) Rock cover thickness and zoning of particles by size; and
(iii) Steepness of underlying slopes.
(e) Individual rock fragments shall be dense, sound, and resistant to abrasion, and free from defects that would tend to unduly increase their destruction by water and frost actions. Weak, friable, or laminated aggregate shall not be used. Shale, rock laminated with shale, and cherts shall not be used.
Rock covering of slopes may not be required where top covers are on the order of ten meters or greater; impoundment slopes are on the order of 10h:1v or less; bulk cover materials have inherently favorable erosion resistance characteristics; and there is negligible drainage catchment area upstream of the pile, and there is good wind protection as described in (a) and (b) of this subsection.
(f) Impoundment surfaces shall be contoured to avoid areas of concentrated surface runoff or abrupt or sharp changes in slope gradient. In addition to rock cover on slopes, areas toward which surface runoff might be directed shall be well protected with substantial rock cover (riprap). In addition to providing for stability of the impoundment systems itself, the overall stability, erosion potential, and geomorphology of surrounding terrain shall be evaluated to assure that there are no processes, such as gully erosion, which would lead to impoundment instability.
(g) The impoundment shall not be located near a capable fault that could cause a maximum credible earthquake larger than that which the impoundment could reasonably be expected to withstand. As used in this criterion, the term "capable fault" has the same meaning as defined in Section III (g) of Appendix A of 10 CFR Part 100. The term "maximum credible earthquake" means that earthquake which would cause the maximum vibratory ground motion based upon an evaluation of earthquake potential considering the regional and local geology and seismology and specific characteristics of local subsurface material.
(h) The impoundment, where feasible, should be designed to incorporate features which will promote deposition of suspended particles. For example, design features which promote deposition of sediment suspended in any runoff which flows into the impoundment area might be utilized; the object of such a design feature would be to enhance the thickness of cover over time.
(5) Criterion 5 - Criteria 5(a) through 5(g) and new Criterion 13 incorporate the basic groundwater protection standards imposed by the United States Environmental Protection Agency in 40 CFR Part 192, Subparts D and E (48 FR 45926; October 7, 1983) which apply during operations and prior to the end of closure. Groundwater monitoring to comply with these standards is required by Criterion 7.
(a) The primary groundwater protection standard is a design standard for surface impoundments used to manage uranium and thorium by-product material. Surface impoundments (except for an existing portion) must have a liner that is designed, constructed, and installed to prevent any migration of wastes out of the impoundment to the adjacent subsurface soil, groundwater, or surface water at any time during the active life (including the closure period) of the impoundment. The liner may be constructed of materials that may allow wastes to migrate into the liner (but not into the adjacent subsurface soil, groundwater, or surface water) during the active life of the facility, provided that impoundment closure includes removal or decontamination of all waste residues, contaminated containment system components (liners, etc.), contaminated subsoils, and structures and equipment contaminated with waste and leachate. For impoundments that will be closed with the liner material left in place, the liner must be constructed of materials that can prevent wastes from migrating into the liner during the active life of the facility.
(b) The liner required by (a) of this subsection must be:
(i) Constructed of materials that have appropriate chemical properties and sufficient strength and thickness to prevent failure due to pressure gradients (including static head and external hydrogeologic forces), physical contact with the waste or leachate to which they are exposed, climatic conditions, the stress of installation, and the stress of daily operation;
(ii) Placed upon a foundation or base capable of providing support to the liner and resistance to pressure gradients above and below the liner to prevent failure of the liner due to settlement, compression, or uplift; and
(iii) Installed to cover all surrounding earth likely to be in contact with the wastes or leachate.
(c) The applicant or licensee will be exempted from the requirements of (a) of this subsection if the department finds, based on a demonstration by the applicant or licensee, that alternate design and operating practices, including the closure plan, together with site characteristics will prevent the migration of any hazardous constituents into groundwater or surface water at any future time. In deciding whether to grant an exemption, the department will consider:
(i) The nature and quantity of the wastes;
(ii) The proposed alternate design and operation;
(iii) The hydrogeologic setting of the facility, including the attenuative capacity and thickness of the liners and soils present between the impoundment and groundwater or surface water; and
(iv) All other factors which would influence the quality and mobility of the leachate produced and the potential for it to migrate to groundwater or surface water.
(d) A surface impoundment must be designed, constructed, maintained, and operated to prevent overtopping resulting from normal or abnormal operations; overfilling; wind and wave actions; rainfall; run-on; from malfunctions of level controllers, alarms, and other equipment; and human error.
(e) When dikes are used to form the surface impoundment, the dikes must be designed, constructed, and maintained with sufficient structural integrity to prevent massive failure of the dikes. In ensuring structural integrity, it must not be presumed that the liner system will function without leakage during the active life of the impoundment.
(f) Uranium and thorium by-product materials must be managed to conform to the following secondary groundwater protection standard: Hazardous constituents entering the groundwater from a licensed site must not exceed the specified concentration limits in the uppermost aquifer beyond the point of compliance during the compliance period. Hazardous constituents are those constituents identified by the department pursuant to (g) of this subsection. Specified concentration limits are those limits established by the department as indicated in (j) of this subsection. The department will also establish the point of compliance and compliance period on a site specific basis through license conditions and orders. The objective in selecting the point of compliance is to provide the earliest practicable warning that the impoundment is releasing hazardous constituents to the groundwater. The point of compliance must be selected to provide prompt indication of groundwater contamination on the hydraulically downgradient edge of the disposal area. The department must identify hazardous constituents, establish concentration limits, set the compliance period, and adjust the point of compliance, if needed, when the detection monitoring established under criterion 7 indicates leakage of hazardous constituents from the disposal area.
(g) A constituent becomes a hazardous constituent subject to (j) of this subsection when the constituent:
(i) Is reasonably expected to be in or derived from the by-product material in the disposal area;
(ii) Has been detected in the groundwater in the uppermost aquifer; and
(iii) Is listed in WAC 246-252-050 Appendix A.
(h) The department may exclude a detected constituent from the set of hazardous constituents on a site specific basis if it finds that the constituent is not capable of posing a substantial present or potential hazard to human health or the environment. In deciding whether to exclude constituents, the department will consider the following:
(i) Potential adverse effect on groundwater quality, considering --
(A) The physical and chemical characteristics of the waste in the licensed site, including its potential for migration;
(B) The hydrogeological characteristics of the facility and surrounding land;
(C) The quantity of groundwater and the direction of groundwater flow;
(D) The proximity and withdrawal rates of groundwater users;
(E) The current and future uses of groundwater in the area;
(F) The existing quality of groundwater, including other sources of contamination and their cumulative impact on the groundwater quality;
(G) The potential for health risks caused by human exposure to waste constituents;
(H) The potential damage to wildlife, crops, vegetation, and physical structures caused by exposure to waste constituents;
(I) The persistence and permanence of the potential adverse effects.
(ii) Potential adverse effects on hydraulically-connected surface water quality, considering --
(A) The volume and physical and chemical characteristics of the waste in the licensed site;
(B) The hydrogeological characteristics of the facility and surrounding land;
(C) The quantity and quality of groundwater, and the direction of groundwater flow;
(D) The patterns of rainfall in the region;
(E) The proximity of the licensed site to surface waters;
(F) The current and future uses of surface waters in the area and any water quality standards established for those surface waters;
(G) The existing quality of surface water, including other sources of contamination and the cumulative impact on surface water quality;
(H) The potential for health risks caused by human exposure to waste constituents;
(I) The potential damage to wildlife, crops, vegetation, and physical structures caused by exposure to waste constituents; and
(J) The persistence and permanence of the potential adverse effects.
(i) In making any determinations under (h) and (k) of this subsection about the use of groundwater in the area around the facility, the department will consider any identification of underground sources of drinking water and exempted aquifers made by the United States Environmental Protection Agency.
(j) At the point of compliance, the concentration of a hazardous constituent must not exceed --
(i) The department approved background concentration of that constituent in the groundwater;
(ii) The respective value given in the table in subsection (5)(l) of this section if the constituent is listed in the table and if the background level of the constituent is below the value listed; or
(iii) An alternate concentration limit established by the department.
(k) Conceptually, background concentrations pose no incremental hazards and the drinking water limits in (j)(i) of this subsection state acceptable hazards but these two options may not be practically achievable at a specific site. Alternate concentration limits that present no significant hazard may be proposed by licensees for department consideration. Licensees must provide the basis for any proposed limits including consideration of practicable corrective actions, that limits are as low as reasonably achievable, and information on the factors the department must consider.
The department will establish a site specific alternate concentration limit for a hazardous constituent as provided in (j) of this subsection if it finds that the constituent will not pose a substantial present or potential hazard to human health or the environment as long as the alternate concentration limit is not exceeded. In establishing alternate concentration limits, the department will apply its as low as reasonably achievable criterion in this chapter. The department will also consider the following factors:
(i) Potential adverse effects on groundwater quality, considering --
(A) The physical and chemical characteristics of the waste in the licensed site including its potential for migration;
(B) The hydrogeological characteristics of the facility and surrounding land;
(C) The quantity of groundwater and the direction of groundwater flow;
(D) The proximity and withdrawal rates of groundwater users;
(E) The current and future uses of groundwater in the area;
(F) The existing quality of groundwater, including other sources of contamination and their cumulative impact on the groundwater quality;
(G) The potential for health risks caused by human exposure to waste constituents;
(H) The potential damage to wildlife, crops, vegetation, and physical structures caused by exposure to waste constituents;
(I) The persistence and permanence of the potential adverse effects.
(ii) Potential adverse effects on hydraulically-connected surface water quality, considering --
(A) The volume and physical and chemical characteristics of the waste in the licensed site;
(B) The hydrogeological characteristics of the facility and surrounding land;
(C) The quantity and quality of groundwater, and the direction of groundwater flow;
(D) The patterns of rainfall in the region;
(E) The proximity of the licensed site to surface waters;
(F) The current and future uses of surface waters in the area and any water quality standards established for those surface waters;
(G) The existing quality of surface water including other sources of contamination and the cumulative impact on surface water quality;
(H) The potential for health risks caused by human exposure to waste constituents;
(I) The potential damage to wildlife, crops, vegetation, and physical structures caused by exposure to waste constituents; and
(J) The persistence and permanence of the potential adverse effects.
(l) MAXIMUM VALUES FOR GROUNDWATER PROTECTION:
Constituent or Property |
Maximum Concentration |
||
| Milligrams per liter |
|||
| Arsenic . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 0.05 | ||
| Barium . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 1.0 | ||
| Cadmium. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 0.01 | ||
| Chromium . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 0.05 | ||
| Lead. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 0.05 | ||
| Mercury . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 0.002 | ||
| Selenium. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 0.01 | ||
| Silver . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 0.05 | ||
| Endrin (1,2,3,4,10,10-hexachloro-1,7 -expoxy- | |||
| 1,4,4a,5,6,7,8,9a-octahydro-1, 4-endo, endo- | |||
| 5,8-dimethano naphthalene). . . . . . . . . . . . . . . . . . | 0.0002 | ||
| Lindane (1,2,3,4,5,6-hexachlorocyclohexane, | |||
| gamma isomer). . . . . . . . . . . . . . . . . . . . . . . . . . . | 0.004 | ||
| Methoxychlor (1,1,1-Trichloro-2,2-bis) | |||
| (p-methoxyphenylethane). . . . . . . . . . . . . . . . . . . . | 0.1 | ||
| Toxaphene (C10H10Cl6, Technical chlorinated | |||
| camphene, 67-69 percent chlorine). . . . . . . . . . . . . | 0.005 | ||
| 2,4-D (2,4-Dichlorophenoxyacetic acid). . . . . . . . . | 0.1 | ||
| 2,4,5-TP Silvex (2,4,5-Trichlorophenoxypropionic | |||
| acid). . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . | 0.01 | ||
| Picocuries per liter | |||
| Combined radium - 226 and radium - 228. . . . . . . . | 5 | ||
| Gross alpha - particle activity (excluding | |||
| radon and uranium when producing uranium | |||
| by-product material or thorium when producing | |||
| thorium by-product material). . . . . . . . . . . . . . . . . . | 15 | ||
(n) In developing and conducting groundwater protection programs, applicants and licensees shall also consider the following:
(i) Installation of bottom liners (where synthetic liners are used, a leakage detection system must be installed immediately below the liner to ensure major failures are detected if they occur. This is in addition to the groundwater monitoring program conducted as provided in Criterion 7. Where clay liners are proposed or relatively thin, in-situ clay soils are to be relied upon for seepage control, tests must be conducted with representative tailings solutions and clay materials to confirm that no significant deterioration of permeability or stability properties will occur with continuous exposure of clay to tailings solutions. Tests must be run for a sufficient period of time to reveal any effects if they are going to occur (in some cases deterioration has been observed to occur rather rapidly after about nine months of exposure)).
(ii) Mill process designs which provide the maximum practicable recycle of solutions and conservation of water to reduce the net input of liquid to the tailings impoundment.
(iii) Dewatering of tailings by process devices and/or in-situ drainage systems (at new sites, tailings must be dewatered by a drainage system installed at the bottom of the impoundment to lower the phreatic surface and reduce the driving head of seepage, unless tests show tailings are not amenable to such a system. Where in-situ dewatering is to be conducted, the impoundment bottom must be graded to assure that the drains are at a low point. The drains must be protected by suitable filter materials to assure that drains remain free running. The drainage system must also be adequately sized to assure good drainage).
(iv) Neutralization to promote immobilization of hazardous constituents.
(o) Where groundwater impacts are occurring at an existing site due to seepage, action must be taken to alleviate conditions that lead to excessive seepage impacts and restore groundwater quality. The specific seepage control and groundwater protection method, or combination of methods, to be used must be worked out on a site-specific basis. Technical specifications must be prepared to control installation of seepage control systems. A quality assurance, testing, and inspection program, which includes supervision by a qualified engineer or scientist, must be established to assure the specifications are met.
(p) In support of a tailings disposal system proposal, the applicant/operator shall supply information concerning the following:
(i) The chemical and radioactive characteristics of the waste solutions.
(ii) The characteristics of the underlying soil and geologic formations particularly as they will control transport of contaminants and solutions. This includes detailed information concerning extent, thickness, uniformity, shape, and orientation of underlying strata. Hydraulic gradients and conductivities of the various formations must be determined. This information must be gathered from borings and field survey methods taken within the proposed impoundment area and in surrounding areas where contaminants might migrate to groundwater. The information gathered on boreholes must include both geologic and geophysical logs in sufficient number and degree of sophistication to allow determining significant discontinuities, fractures, and channeled deposits of high hydraulic conductivity. If field survey methods are used, they should be in addition to and calibrated with borehole logging. Hydrologic parameters such as permeability may not be determined on the basis of laboratory analysis of samples alone; a sufficient amount of field testing (e.g., pump tests) must be conducted to assure actual field properties are adequately understood. Testing must be conducted to allow estimating chemi-sorption attenuation properties of underlying soil and rock.
(iii) Location, extent, quality, capacity and current uses of any groundwater at and near the site.
(q) Steps must be taken during stockpiling of ore to minimize penetration of radionuclides into underlying soils; suitable methods include lining and/or compaction of ore storage areas.
(6) Criterion 6 - (a) In disposing of waste by-product material, licensees shall place an earthen cover (or approved alternative) over tailings or wastes at the end of milling operations and shall close the waste disposal area in accordance with a design1 which provides reasonable assurance of control of radiological hazards to:
(i) Be effective for 1,000 years, to the extent reasonably achievable, and, in any case, for at least 200 years; and
(ii) Limit releases of Radon-222 from uranium by-product materials, and Radon-220 from thorium by-product materials, to the atmosphere so as not to exceed an average2 release rate of 20 picocuries per square meter per second (pCi/m2s) to the extent practicable throughout the effective design life determined pursuant to (a)(i) of this subsection (this criterion). In computing required tailings cover thicknesses, moisture in soils in excess of amounts found normally in similar soils in similar circumstances may not be considered. Direct gamma exposure from the tailings or wastes should be reduced to background levels. The effects of any thin synthetic layer may not be taken into account in determining the calculated radon exhalation level. If nonsoil materials are proposed as cover materials, it must be demonstrated that these materials will not crack or degrade by differential settlement, weathering, or other mechanism, over long-term intervals.
(b) As soon as reasonably achievable after emplacement of the final cover to limit releases of Radon-222 from uranium by-product material and prior to placement of erosion protection barriers or other features necessary for long-term control of the tailings, the licensees shall verify through appropriate testing and analysis that the design and construction of the final radon barrier is effective in limiting releases of Radon-222 to a level not exceeding 20 pCi/m2s averaged over the entire pile or impoundment using the procedures described in 40 CFR part 61, appendix B, Method 115, or another method of verification approved by the Nuclear Regulatory Commission as being at least as effective in demonstrating the effectiveness of the final radon barrier.
(c) When phased emplacement of the final radon barrier is included in the applicable reclamation plan, the verification of Radon-222 release rates required in (b) of this subsection (this criterion) must be conducted for each portion of the pile or impoundment as the final radon barrier for that portion is emplaced.
(d) Within ninety days of the completion of all testing and analysis relevant to the required verification in (b) and (c) of this subsection (this criterion), the uranium mill licensee shall report to the department the results detailing the actions taken to verify that levels of release of Radon-222 do not exceed 20 pCi/m2s when averaged over the entire pile or impoundment. The licensee shall maintain records until termination of the license documenting the source of input parameters including the results of all measurements on which they are based, the calculations and/or analytical methods used to derive values for input parameters, and the procedure used to determine compliance. These records shall be kept in a form suitable for transfer to the custodial agency at the time of transfer of the site to DOE or a state for long-term care if requested.
(e) Near surface cover materials (i.e., within the top three meters) may not include waste or rock that contains elevated levels of radium; soils used for near surface cover must be essentially the same, as far as radioactivity is concerned, as that of surrounding surface soils. This is to ensure that surface radon exhalation is not significantly above background because of the cover material itself.
(f) The design requirements in this criterion for longevity and control of radon releases apply to any portion of a licensed and/or disposal site unless such portion contains a concentration of radium in land, averaged over areas of 100 square meters, which, as a result of by-product material, does not exceed the background level by more than:
(i) 5 picocuries per gram (pCi/g) of radium-226, or, in the case of thorium by-product material, radium-228, averaged over the first 15 centimeters (cm) below the surface; and
(ii) 15 pCi/g of radium-226, or, in the case of thorium by-product material, radium-228, averaged over 15-cm thick layers more than 15 cm below the surface.
(g) The licensee shall also address the nonradiological hazards associated with the wastes in planning and implementing closure. The licensee shall ensure that disposal areas are closed in a manner that minimizes the need for further maintenance. To the extent necessary to prevent threats to human health and the environment, the licensee shall control, minimize, or eliminate post-closure escape of nonradiological hazardous constituents, leachate, contaminated rainwater, or waste decomposition products to the ground or surface waters or to the atmosphere.
| 1 | In the case of thorium by-product materials, the standard applies only to design. Monitoring for radon emissions from thorium by-product materials after installation of an appropriately designed cover is not required. |
| 2 | This average applies to the entire surface of each disposal area over a period of at least one year, but a period short compared to 100 years. Radon will come from both by-product materials and from covering materials. Radon emissions from covering materials should be estimated as part of developing a closure plan for each site. The standard, however, applies only to emissions from by-product materials to the atmosphere. |
(b) The department may approve a licensee's request to extend the time for performance of milestones related to emplacement of the final radon barrier if, after providing an opportunity for public participation, the department finds that the licensee has adequately demonstrated in the manner required in subsection (6)(b) of this section (Criterion 6) that releases of Radon-222 do not exceed an average of 20 pCi/m2s. If the delay is approved on the basis that the radon releases do not exceed 20 pCi/m2s, a verification of radon levels, as required by subsection (6)(b) of this section (Criterion 6), must be made annually during the period of delay. In addition, once the department has established the date in the reclamation plan for the milestone for completion of the final radon barrier, the department may extend that date based on cost if, after providing an opportunity for public participation, the department finds that the licensee is making good faith efforts to emplace the final radon barrier, the delay is consistent with the definitions of available technology, and the radon releases caused by the delay will not result in a significant incremental risk to the public health.
(c) The department may authorize by license amendment, upon licensee request, a portion of the impoundment to accept uranium by-product material or such materials that are similar in physical, chemical, and radiological characteristics to the uranium mill tailings and associated wastes already in the pile or impoundment from other sources, during the closure process. No such authorization will be made if it results in a delay or impediment to emplacement of the final radon barrier over the remainder of the impoundment in a manner that will achieve levels of Radon-222 releases not exceeding 20 pCi/m2s averaged over the entire impoundment. The verification required in subsection (6)(b) of this section (Criterion 6) may be completed with a portion of the impoundment being used for further disposal if the department makes a final finding that the impoundment will continue to achieve a level of Radon-222 releases not exceeding 20 pCi/m2s averaged over the entire impoundment. In this case, after the final radon barrier is complete except for the continuing disposal area:
(i) Only by-product material will be authorized for disposal;
(ii) The disposal will be limited to the specified existing disposal area; and
(iii) This authorization will only be made after providing opportunity for public participation.
Reclamation of the disposal area, as appropriate, must be completed in a timely manner after disposal operations cease in accordance with subsection (6)(a) of this section (Criterion 6); however, these actions are not required to be complete as part of meeting the deadline for final radon barrier construction.
(7) Criterion 7 - At least one full year prior to any major site construction, a preoperational monitoring program must be conducted to provide complete baseline data on a milling site and its environs. Throughout the construction and operating phases of the mill, an operational monitoring program must be conducted to complete the following:
(a) To measure or evaluate compliance with applicable standards and regulations;
(b) To evaluate performance of control systems and procedures;
(c) To evaluate environmental impacts of operation; and
(d) To detect potential long-term effects.
The licensee shall establish a detection monitoring program needed for the department to set the site-specific groundwater protection standards in Criterion 5 of this section. For all monitoring under this paragraph, the licensee or applicant will propose for department approval as license conditions, which constituents are to be monitored on a site-specific basis. A detection monitoring program has two purposes. The initial purpose of the program is to detect leakage of hazardous constituents from the disposal area so that the need to set groundwater protection standards is monitored. If leakage is detected, the second purpose of the program is to generate data and information needed for the department to establish the standards under Criterion 5. The data and information must provide a sufficient basis to identify those hazardous constituents which require concentration limit standards and to enable the department to set the limits for those constituents and the compliance period. They may also need to provide the basis for adjustments to the point of compliance. For licenses in effect September 30, 1983, the detection monitoring programs must have been in place by October 1, 1984. For licenses issued after September 30, 1983, the detection monitoring programs must be in place when specified by the department in orders or license conditions. Once groundwater protection standards have been established pursuant to Criterion 5, the licensee shall establish and implement a compliance monitoring program. The purpose of the compliance monitoring program is to determine that the hazardous constituent concentrations in ground water continue to comply with the standards set by the department. In conjunction with a corrective action program, the licensee shall establish and implement a corrective action monitoring program. The purpose of the corrective action monitoring program is to demonstrate the effectiveness of the corrective actions. Any monitoring program required by this paragraph may be based on existing monitoring programs to the extent the existing programs can meet the stated objective for the program.
(8) Criterion 8 - Milling operations shall be conducted so that all airborne effluent releases are reduced to as low as is reasonably achievable. The primary means of accomplishing this shall be by means of emission controls. Institutional controls, such as extending the site boundary and exclusion area, may be employed to ensure that offsite exposure limits are met, but only after all practicable measures have been taken to control emissions at the source. Notwithstanding the existence of individual dose standards, strict control of emissions is necessary to assure that population exposures are reduced to the maximum extent reasonably achievable and to avoid site contamination. The greatest potential sources of offsite radiation exposure (aside from radon exposure) are dusting from dry surfaces of the tailings disposal area not covered by tailings solution and emissions from yellowcake drying and packaging operations. During operations and prior to closure, radiation doses from radon emissions from surface impoundments shall be kept as low as is reasonably achievable. Checks shall be made and logged hourly of all parameters (e.g., differential pressure and scrubber water flow rate) which determine the efficiency of yellowcake stack emission control equipment operation. It shall be determined whether or not conditions are within a range prescribed to ensure that the equipment is operating consistently near peak efficiency; corrective action shall be taken when performance is outside of prescribed ranges. Effluent control devices shall be operative at all times during drying and packaging operations and whenever air is exhausting from the yellowcake stack.
Drying and packaging operations shall terminate when controls are inoperative. When checks indicate the equipment is not operating within the range prescribed for peak efficiency, actions shall be taken to restore parameters to the prescribed range. When this cannot be done without shutdown and repairs, drying and packaging operations shall cease as soon as practicable.
Operations may not be restarted after cessation due to off-normal performance until needed corrective actions have been identified and implemented. All such cessations, corrective actions, and restarts shall be reported to the department in writing, within ten days of the subsequent restart.
To control dusting from tailings, that portion not covered by standing liquids shall be wetted or chemically stabilized to prevent or minimize blowing and dusting to the maximum extent reasonably achievable. This requirement may be relaxed if tailings are effectively sheltered from wind, such as may be the case where they are disposed of below grade and the tailings surface is not exposed to wind. Consideration shall be given in planning tailings disposal programs to methods which would allow phased covering and reclamation of tailings impoundments since this will help in controlling particulate and radon emissions during operation. To control dustings from diffuse sources, such as tailings and ore pads where automatic controls do not apply, operators shall develop written operating procedures specifying the methods of control which will be utilized.
Milling operations producing or involving thorium by-product material shall be conducted in such a manner as to provide reasonable assurance that the annual dose equivalent does not exceed twenty-five millirems to the whole body, seventy-five millirems to the thyroid, and twenty-five millirems to any other organ of any member of the public as a result of exposures to the planned discharge of radioactive materials, Radon-220 and its daughters excepted, to the general environment.
Uranium and thorium by-product materials shall be managed so as to conform to the applicable provisions of Title 40 of the Code of Federal Regulations, Part 440, Ore Mining and Dressing Point Source Category: Effluent Limitations Guidelines and New Source Performance Standards, Subpart C, Uranium, Radium, and Vanadium Ores Subcategory, as codified on January 1, 1983.
The licensee shall establish a detection monitoring program needed to establish the groundwater protection standards in subsection (5)(f) of this section. A detection monitoring program has two purposes. The initial purpose of the program is to detect leakage of hazardous constituents from the disposal area so that the need to set groundwater protection standards is monitored. If leakage is detected, the second purpose of the program is to generate data and information needed for the department to establish the standards under subsection (5)(f) of this section. The data and information must provide a sufficient basis to identify those hazardous constituents which require concentration limit standards and to enable the department to set the limits for those constituents and the compliance period. They may also need to provide the basis for adjustments to the point of compliance. For licenses in effect September 30, 1983, the detection monitoring programs must have been in place by October 1, 1984. For licenses issued after September 30, 1983, the detection monitoring programs must be in place when specified by the department in orders or license conditions. Once groundwater protection standards have been established pursuant to subsection (5)(f) of this section, the licensee shall establish and implement a compliance monitoring program. The purpose of the compliance monitoring program is to determine that the hazardous constituent concentrations in groundwater continue to comply with the standards set by the department. In conjunction with a corrective action program, the licensee shall establish and implement a corrective action monitoring program. The purpose of the corrective action monitoring program is to demonstrate the effectiveness of the corrective actions. Any monitoring program required by this paragraph may be based on existing monitoring programs to the extent the existing programs can meet the stated objective for the program.
Daily inspections of tailings or waste retention systems must be conducted by a qualified engineer or scientist and documented. The department must be immediately notified of any failure in a tailings or waste retention system which results in a release of tailings or waste into unrestricted areas, and/or of any unusual conditions (conditions not contemplated in the design of the retention system) which if not corrected could indicate the potential or lead to failure of the system and result in a release of tailings or waste into unrestricted areas.
(9) Criterion 9 - (a) Pursuant to chapter 70.121 RCW, and except as otherwise provided, financial surety arrangements for site reclamation and long-term surveillance and control which may consist of surety bonds, cash deposits, certificates of deposit, deposits of government securities, irrevocable letters or lines of credit, or any combination of the above, or other arrangements approved by the department, milling operations shall be established for source material to ensure the protection of the public health and safety in the event of abandonment, default, or other inability of the licensee to meet the requirements of the act and these regulations.
(i) The amount of funds to be ensured by such surety arrangements shall be based on department-approved cost estimates.
(ii) Self-insurance, or any arrangement which essentially constitutes self-insurance (e.g., a contract with a state or federal agency), will not satisfy the surety requirement, since this provides no additional assurance other than that which already exists through license requirements.
(b) The arrangements required in (a) of this subsection shall be established prior to commencement of operations to assure that sufficient funds will be available to carry out decontamination and decommissioning of the facility.
(c) Amendments to licenses in effect on the effective date of this regulation may be issued, providing that the required surety arrangements are established within ninety days after the effective date of this subsection.
(d) For source material milling operations, the amount of funds to be ensured by such surety arrangements shall be based on department-approved cost estimates in an approved plan for (i) decontamination and decommissioning of mill buildings and the milling site to levels which would allow unrestricted use of these areas upon decommissioning, and (ii) the reclamation of tailings and/or waste disposal areas in accordance with the technical criteria delineated in this section. The licensee shall submit this plan in conjunction with an environmental report that addresses the expected environmental impacts of the milling operation, decommissioning and tailings reclamation, and evaluates alternatives for mitigating these impacts. In addition, the surety shall cover the payment of the charge for long-term surveillance and control required by the department. In establishing specific surety arrangements, the licensee's cost estimates shall take into account total costs that would be incurred if an independent contractor were hired to perform the decommissioning and reclamation work. In order to avoid unnecessary duplication and expense, the department may accept financial sureties that have been consolidated with financial or surety arrangements established to meet requirements of other federal or state agencies and/or local governing bodies for such decommissioning, decontamination, reclamation, and long-term site surveillance, provided such arrangements are considered adequate to satisfy these requirements and that portion of the surety which covers the decommissioning and reclamation of the mill, mill tailings site and associated areas, and the long-term funding charge is clearly identified and committed for use in accomplishing these activities. The licensee's surety mechanism will be reviewed annually by the department to assure that sufficient funds will be available for completion of the reclamation plan if the work had to be performed by an independent contractor. The amount of surety liability should be adjusted to recognize any increases or decreases resulting from inflation, changes in engineering plans, activities performed, and any other conditions affecting costs. Regardless of whether reclamation is phased through the life of the operation or takes place at the end of operations, an appropriate portion of surety liability shall be retained until final compliance with the reclamation plan is determined. This will yield a surety that is at least sufficient at all times to cover the costs of decommissioning and reclamation of the areas that are expected to be disturbed before the next license renewal. The term of the surety mechanism must be open ended, unless it can be demonstrated that another arrangement would provide an equivalent level of assurance. This assurance could be provided with a surety instrument which is written for a specific period of time (e.g., five years), yet which must be automatically renewed unless the surety notifies the beneficiary (the state regulatory agency) and the principal (the licensee) some reasonable time (e.g., ninety days) prior to the renewal date of their intention not to renew. In such a situation, the surety requirement still exists and the licensee would be required to submit an acceptable replacement surety within a brief period of time to allow at least sixty days for the department to collect.
Proof of forfeiture must not be necessary to collect the surety so that in the event that the licensee could not provide an acceptable replacement surety within the required time, the surety shall be automatically collected prior to its expiration. The conditions described above would have to be clearly stated on any surety instrument which is not open-ended and must be agreed to by all parties.
Long-term care requirements. Pursuant to chapter 70.121 RCW, and as otherwise provided in WAC ((246-235-080 (6)(d)))
246-235-086(4), a long-term care trust fund shall be established
by source material milling licensees prior to the issuance of the
license.
(10) Criterion 10 - (a) A minimum charge of two hundred
fifty thousand dollars (1978 United States dollars) accrued as
specified in WAC ((246-235-080 (6)(d))) 246-235-086(4) to cover
the costs of long-term surveillance shall be paid by each mill
operator to the agency prior to the termination of a uranium or
thorium mill license. If site surveillance or control
requirements at a particular site are determined, on the basis of
a site-specific evaluation, to be significantly greater than
those specified in (a) of this subsection (e.g., if fencing is
determined to be necessary), variance in funding requirements may
be specified by the department. The total charge to cover the
costs of long-term surveillance shall be such that, with an
assumed one percent annual real interest rate, the collected
funds will yield interest in an amount sufficient to cover the
annual costs of site surveillance. The charge will be adjusted
annually prior to actual payments to recognize inflation. The
inflation rate to be used is that indicated by the change in the
consumer price index published by the United States Department of
Labor, Bureau of Labor Statistics. Contributions by a licensee
to the long-term care trust fund pursuant to chapter 70.121 RCW
shall be transferred to cover the costs assessed under this
criterion.
(11) Criterion 11 - These criteria relating to ownership of tailings and their disposal sites become effective on November 8, 1981, and apply to all licenses terminated, issued, or renewed after that date.
Any uranium or thorium milling license or tailings license shall contain such terms and conditions as the United States Nuclear Regulatory Commission determines necessary to assure that prior to termination of the license, the licensee will comply with ownership requirements of this criterion for sites used for tailings disposal.
Title to the by-product material licensed pursuant to WAC 246-252-030 and land, including any interests therein (other than land owned by the United States or by the state of Washington) which is used for the disposal of any such by-product material, or is essential to ensure the long-term stability of such disposal site, shall be transferred to the United States or the state of Washington. In view of the fact that physical isolation must be the primary means of long-term control, and government land ownership is a desirable supplementary measure, ownership of certain severable subsurface interests (for example, mineral rights) may be determined to be unnecessary to protect the public health and safety and the environment. In any case, the applicant/operator must demonstrate a serious effort to obtain such subsurface rights, and must, in the event that certain rights cannot be obtained, provide notification in local public land records of the fact that the land is being used for the disposal of radioactive material and is subject to either a United States Nuclear Regulatory Commission general or specific license prohibiting the disruption and disturbance of the tailings. In some rare cases, such as may occur with deep burial where no ongoing site surveillance will be required, surface land ownership transfer requirements may be waived. For licenses issued before November 8, 1981, the United States Nuclear Regulatory Commission may take into account the status of the ownership of such land, and interests therein, and the ability of a licensee to transfer title and custody thereof to the United States or the state. If the United States Nuclear Regulatory Commission, subsequent to title transfer, determines that use of the surface or subsurface estates, or both, of the land transferred to the United States or to a state will not endanger the public health, safety, welfare or environment, the United States Nuclear Regulatory Commission may permit the use of the surface or subsurface estates, or both, of such land in a manner consistent with the provisions provided in these criteria. If the United States Nuclear Regulatory Commission permits such use of such land, it will provide the person who transferred such land with the right of first refusal with respect to such use of such land.
Material and land transferred to the United States or a state in accordance with this criterion must be transferred without cost to the United States or a state other than administrative and legal costs incurred in carrying out such transfer.
The provisions of this part, respecting transfer of title and custody to land and tailings and wastes, do not apply in the case of lands held in trust by the United States for any Indian tribe, or lands owned by such Indian tribe subject to a restriction against alienation imposed by the United States. In the case of such lands which are used for the disposal of by-product material, as defined in this section, the licensee shall enter into arrangements with the United States Nuclear Regulatory Commission as may be appropriate to assure the long-term surveillance of such lands by the United States.
(12) Criterion 12 - The final disposition of tailings or wastes at milling sites should be such that ongoing active maintenance is not necessary to preserve isolation. As a minimum, annual site inspections must be conducted by the government agency retaining ultimate custody of the site where tailings or wastes are stored, to confirm the integrity of the stabilized tailings or waste systems, and to determine the need, if any, for maintenance and/or monitoring. Results of the inspection must be reported to the United States Nuclear Regulatory Commission within sixty days following each inspection. The United States Nuclear Regulatory Commission may require more frequent site inspections if, on the basis of a site-specific evaluation, such a need appears necessary, due to the features of a particular tailings or waste disposal system.
(13) Criterion 13 - Secondary groundwater protection standards required by Criterion 5 of this section are concentration limits for individual hazardous constituents. The list of constituents found in Appendix A of this chapter, chapter 246-252 WAC, identifies the constituents for which standards must be set and complied with if the specific constituent is reasonably expected to be in or derived from the by-product material and has been detected in groundwater. For purposes of this criterion, the property of gross alpha activity will be treated as if it is a hazardous constituent. Thus, when setting standards under subsection (5)(j) of this section, the department will also set a limit for gross alpha activity.
[Statutory Authority: RCW 70.98.050. 97-13-055, § 246-252-030, filed 6/16/97, effective 7/17/97; 94-01-073, § 246-252-030, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. 91-16-109 (Order 187), § 246-252-030, filed 8/7/91, effective 9/7/91. Statutory Authority: RCW 43.70.040. 91-02-049 (Order 121), recodified as § 246-252-030, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. 87-01-031 (Order 2450), § 402-52-100, filed 12/11/86. Statutory Authority: Chapter 70.121 RCW. 81-16-031 (Order 1683), § 402-52-100, filed 7/28/81.]
OTS-3597.3
AMENDATORY SECTION(Amending WSR 98-13-037, filed 6/8/98,
effective 7/9/98)
WAC 246-235-080
Special requirements for issuance of
((certain)) specific licenses for medical use of radioactive
material.
(1) Human use of radioactive material in institutions. In addition to the requirements set forth in WAC 246-235-020 a specific license for human use of radioactive material in institutions will be issued if:
(a) The applicant has appointed a radiation safety committee to coordinate the use of radioactive material throughout that institution and to maintain surveillance over the institution's radiation safety program. Membership of the committee should include a specialist (where applicable a physician) from each department where radioactive material is used, a representative of the institution's management, a representative of the nursing staff, and a person trained in radiation safety. The radiation safety committee shall meet at least quarterly. Minutes shall be taken and maintained for two years for inspection by the department;
(b) The applicant possesses adequate facilities for the clinical care of patients. The applicant is advised that construction of new radioisotope facilities and modification of existing facilities must also comply with the requirements of WAC 246-318-660 of the construction review section of the department;
(c) The physician(s) designated on the application as the individual user(s) has (or have) substantial experience in the handling and administration of radioactive material and, where applicable, the clinical management of radioactive patients; and
(d) If the application is for a license to use unspecified quantities or multiple types of radioactive material, the applicant's staff has substantial experience in the use of a variety of radioactive materials for a variety of human uses.
(2) Licensing of individual physicians for human use of radioactive material. In addition to the requirements set forth in WAC 246-235-020 a specific license for the human use of radioactive material will be issued to an individual physician if:
(a) The applicant has access to a hospital possessing adequate facilities to hospitalize and monitor the applicant's radioactive patients whenever it is advisable;
(b) The applicant has extensive experience in the handling and administration of radioactive material and, where applicable, the clinical management of radioactive patients;
(c) The application is for use in the applicant's practice in an office outside a medical institution; and
(d) ((The department will approve an application)) If the
application is for use by an individual physician or group of
physicians for a specific license to receive, possess or use
radioactive material on the premises of a medical institution,
the department will issue a specific license only if:
(i) The use of radioactive material is limited to the:
(A) Administration of radiopharmaceuticals for diagnostic or therapeutic purposes;
(B) Performance of diagnostic studies on patients to whom a radiopharmaceutical has been administered;
(C) Performance of in vitro diagnostic studies; or
(D) Calibration and quality control checks of radioactive assay instrumentation, radiation safety instrumentation and diagnostic instrumentation;
(ii) The physician brings the radioactive material with him or her and removes the radioactive material when he or she departs. (The institution cannot receive, possess or store radioactive material other than the amount of material remaining in the patient); and
(iii) The medical institution does not hold a radioactive material license issued pursuant to the provisions of subsection (1) of this section.
(3) Specific licenses for certain groups of medical uses of radioactive material.
(a) Subject to the provisions of (b), (c) and (d) of this subsection an application for a specific license pursuant to subsection (1), (2) or (4) of this section, or for any medical use or uses of radioactive material specified in one or more of Groups I to VI, inclusive, of WAC 246-235-120, Schedule A, will be approved for all of the uses within the group or groups which include the use or uses specified in the application if:
(i) The applicant satisfies the requirements of subsection (1), (2) or (4) of this section;
(ii) The applicant, or the physician designated in the application as the individual user, has adequate clinical experience in the types of uses included in the group or groups;
(iii) The applicant, or the physicians and all other personnel who will be involved in the preparation and use of the radioactive material, have adequate training and experience in the handling of radioactive material appropriate to their participation in the uses included in the group or groups;
(iv) The applicant's radiation detection and measuring instrumentation is adequate for conducting the procedures involved in the uses included in the group or groups, specifically:
(A) For Groups I through V, applicant must possess and use a calibrated and operable low-range survey instrument with a thin window (less than 7 mg/cm2) capable of detecting radiation levels of 0.05 milliroentgen per hour up to at least 20 milliroentgens per hour;
(B) For Groups III, V, and VI, applicant must possess a calibrated and operable high-range survey instrument capable of detecting radiation levels up to at least one Roentgen per hour;
(v) The applicant's radiation safety operating procedures are adequate for handling and disposal of the radioactive material involved in the uses included in the group or groups.
(b) Any licensee or registrant who is authorized to use radioactive material pursuant to one or more groups in (a) of this subsection and WAC 246-235-120, Schedule A, is subject to the following conditions:
(i) For Groups I, II, IV, and V, no licensee or registrant shall receive, possess or use radioactive material except as a radiopharmaceutical manufactured in the form to be administered to the patient, labeled, packaged and distributed in accordance with a specific license issued by the department pursuant to WAC 246-235-100, a specific license issued by the United States Nuclear Regulatory Commission pursuant to Section 32.72 of 10 CFR Part 32, or a specific license issued by an agreement state or a licensing state pursuant to equivalent regulations.
(ii) For Group III, no licensee or registrant shall receive,
possess or use generators or reagent kits containing radioactive
material unless manufactured, labeled, packaged and distributed
in accordance with a specific license issued by the department
pursuant to WAC 246-235-100, a specific license issued by the
United States Nuclear Regulatory Commission ((pursuant to)) under
Section 32.73 of 10 CFR Part 32, or a specific license issued by
an agreement state or a licensing state ((pursuant to)) under
equivalent regulations.
(iii) For Group VI, no licensee or registrant shall receive,
possess or use radioactive material except as contained in a
source or device that has been manufactured, labeled, packaged
and distributed in accordance with a specific license issued by
the department ((pursuant to)) under WAC 246-235-102, a specific
license issued by the United States Nuclear Regulatory Commission
((pursuant to)) under Section 32.74 of 10 CFR Part 32, or a
specific license issued to the manufacturer by an agreement state
or a licensing state ((pursuant to)) under equivalent
regulations.
(iv) For Group III, any licensee or registrant who uses
generators or reagent kits shall elute the generator or process
radioactive material with the reagent kit in accordance with
instructions ((which are)) approved by the department, the United
States Nuclear Regulatory Commission, an agreement state or a
licensing state and are furnished by the manufacturer on the
label attached to or in the leaflet or brochure which accompanies
the generator or reagent kit.
(c) Any licensee who is licensed ((pursuant to)) under (a)
of this subsection for one or more of the medical use groups in
WAC 246-235-120, Schedule A, also is authorized, subject to the
provisions of (c) and (d) of this subsection to receive, possess
and use for calibration and reference standards:
(i) Any radioactive material authorized for use under Group I, Group II, or Group III of WAC 246-235-120, Schedule A, with a half-life not longer than one hundred days, in amounts not to exceed 15 millicuries total;
(ii) Any radioactive material authorized for use under Group I, Group II, or Group III of WAC 246-235-120, Schedule A, with half-life greater than one hundred days in amounts not to exceed 200 microcuries total;
(iii) Technetium-99m in amounts not to exceed 50 millicuries;
(iv) Any radioactive material excluding Radium-226, in amounts not to exceed fifteen millicuries per sealed source, contained in calibration or reference sources that have been manufactured, labeled, packaged, and distributed in accordance with a specific license issued by the department pursuant to WAC 246-235-102, a specific license issued by the United States Nuclear Regulatory Commission pursuant to Section 32.74 of 10 CFR Part 32, or a specific license issued to the manufacturer by an agreement state or a licensing state pursuant to equivalent regulations.
(d) Leak tests.
(i) Any licensee or registrant who possesses sealed sources
as calibration or reference sources ((pursuant to)) under (c) of
this subsection shall cause each sealed source containing
radioactive material, other than Hydrogen-3, with a half-life
greater than thirty days in any form other than gas to be tested
for leakage and/or contamination at intervals not to exceed six
months. In the absence of a certificate from a transferor
indicating that a test has been made within six months prior to
the transfer, the sealed sources shall not be used until
tested((: Provided, however, That no leak)). However, leak
tests are not required when:
(A) The source contains 100 microcuries or less of beta and/or gamma emitting material or 10 microcuries or less of alpha emitting material;
(B) The sealed source is stored and is not being used:
Provided, ((That)) a physical inventory of the source and wipe
surveys of the storage area or storage container are conducted.
(ii) The leak test shall be capable of detecting the presence of 0.005 microcurie of radioactive material on the test sample. The test sample shall be taken from the sealed source or from the surfaces of the device in which the sealed source is mounted or stored on which contamination might be expected to accumulate. Records of leak test results shall be kept in units of microcuries and maintained for inspection by the department.
(iii) If the leak test reveals the presence of 0.005 microcurie or more of removable contamination, the licensee or registrant shall immediately withdraw the sealed source from use and shall cause it to be decontaminated and repaired or to be disposed of in accordance with chapters 246-235 and 246-221 WAC. A report shall be filed within five days of the test with the department describing the equipment involved, the test results, and the corrective action taken.
(e) Any licensee or registrant who possesses and uses
calibration and reference sources ((pursuant to)) under (c)(iv)
of this subsection shall:
(i) Follow the radiation safety and handling instructions
approved by the department, the United States Nuclear Regulatory
Commission, an agreement state or a licensing state and furnished
by the manufacturer on the label attached to the source, or
permanent container thereof, or in the leaflet or brochure that
accompanies the source, and maintain ((such)) the instructions in
a legible and conveniently available form; and
(ii) Conduct a quarterly physical inventory to account for all sources received and possessed. Records of the inventories shall be maintained for inspection by the department and shall include at a minimum the quantities and kinds of radioactive material, location of sources, name of person performing the inventory, and the date of the inventory.
(4) Human use of sealed sources. In addition to the requirements set forth in WAC 246-235-020, a specific license for human use of sealed sources will be issued only if the individual applicant or, if the application is made by an institution, the individual user:
(a) Has specialized training in the diagnostic or therapeutic use of the sealed source considered, or has experience equivalent to such training; and
(b) Is a physician.
(((5) Use of sealed sources in industrial radiography. In
addition to the requirements set forth in WAC 246-235-020, a
specific license for use of sealed sources in industrial
radiography will be issued if:
(a) The applicant will have an adequate program for training radiographers and radiographer's assistants and submits to the department a schedule or description of such program which specifies the:
(i) Initial training;
(ii) Periodic training;
(iii) On-the-job training;
(iv) Means to be used by the licensee to determine the radiographer's knowledge and understanding of and ability to comply with department regulations and licensing requirements, and the operating and emergency procedures of the applicant; and
(v) Means to be used by the licensee to determine the radiographer's assistant's knowledge and understanding of and ability to comply with the operating and emergency procedures of the applicant;
(b) The applicant submits to the department and complies with satisfactory written operating and emergency procedures (described in WAC 246-243-140);
(c) The applicant will have a quarterly internal inspection system, to assure that license provisions, regulations, and the applicant's operating and emergency procedures are followed by radiographers and radiographer's assistants. Records of this management control program shall be maintained for two years;
(d) The applicant submits to the department a description of the applicant's overall organizational structure pertaining to the industrial radiography program, including specified delegations of authority and responsibility for operation of the program;
(e) The applicant who desires to conduct leak tests has established adequate procedures to be followed in leak testing sealed sources for possible leakage and contamination and submits to the department a description of such procedures including:
(i) Instrumentation to be used;
(ii) Method of performing tests, e.g., points on equipment to be smeared and method of taking smear; and
(iii) Pertinent experience of the person who will perform the tests;
(f) The licensee shall conduct a program for inspection and maintenance of radiographic exposure devices and storage containers to assure proper functioning of components important to safety.
(6) Environmentally significant licensing actions. In addition to the requirements set forth in WAC 246-235-020, a specific license for any activity within the licensing authority of the department which the department determines will significantly affect the radiological quality of the human environment, including those specified in WAC 197-11-845(1) and 246-03-030 (1)(a)(ii) (i.e., licenses to operate low level waste burial facilities or licenses to operate or expand beyond the design capacity, mineral processing facilities or their tailings areas, whose products, or byproducts, have concentrations of naturally occurring radioactive material in excess of exempt concentrations as specified in WAC 246-232-130, Schedule C), will be issued if the following conditions are met:
(a) Environmental impact statement.
(i) The application for a license or license amendment (other than administrative amendments) is accompanied or preceded by a final environmental impact statement or final declaration of nonsignificance completed in accordance with the State Environmental Policy Act (SEPA) procedures and guidelines specified in chapters 197-11 and 246-03 WAC. For any uranium or thorium mill in operation on or before the effective date of this regulation for which an environmental impact statement has not been prepared previously, an application for license renewal must be accompanied or preceded by a final environmental impact statement or final declaration of nonsignificance completed in accordance with SEPA guidelines.
(A) Alternative sites to those chosen by the applicant shall include all alternative sites, whether or not those sites are under the control or ownership of the applicant.
(B) Long term impacts shall include, but not be limited to, decommissioning, decontamination, reclamation impacts and material management associated with the proposed activities.
(C) Environmental reviews, dose assessments, ecology, construction effects on biota, impact on the environment from the use of chemicals, and socioeconomic effects shall be addressed.
(D) Alternative disposal sites and techniques for disposal shall be evaluated to determine if a site or technique is clearly superior.
(b) For uranium or thorium milling operations, a bond made payable to the department of health or other acceptable government agency, and in an amount specified by the department, shall be posted to ensure the protection of the public health and safety in the event of abandonment, default or other inability of the licensee to meet the requirements for reclamation and disposal of tailings and for decommissioning the site. The bond, or a copy thereof when the bond is made payable to another government agency, shall be received by the department prior to issuance of the license, or prior to license renewal for mills in operation on or before the effective date of this regulation. Other acceptable surety arrangements in addition to surety bonding include cash deposits, certificates of deposit, deposits of government securities, letters or lines of credit or combinations of the foregoing. The amount and mechanism of the surety arrangement may be reviewed by the department preceding each license renewal and adjustments may be required of the licensee prior to such renewal.
(c) The owner of the proposed uranium or thorium mill and tailings site(s) agrees to transfer or revert to the appropriate state or federal agency upon termination of the license, all lands, buildings and grounds, and any interest therein, necessary to fulfill the purposes of this subsection, except where the lands are held in trust for, or are owned by any Indian tribe. For any uranium or thorium mill in operation on or before the effective date of this regulation, such an agreement will be required prior to license renewal.
(d) For all uranium and thorium milling operations, the owner or operator shall arrange to pay to the department or its designee a fee in accordance with WAC 246-254-150 for a special security fund for the further maintenance, surveillance or care which may be required after a licensee has ceased to operate.
A minimum fund of two hundred fifty thousand dollars shall be provided by the licensee payable to the state. If a shortfall exists between the amount of money in the special security fund and the two hundred fifty thousand dollars minimum amount, a surety bond, or other acceptable surety instrument as defined above shall be arranged.
(e) The application for a license includes a description of an appropriate program for effluent monitoring, environmental monitoring and data reporting. Such description shall encompass locations, frequency, and types of sampling, analytical plans and procedures, minimum detection levels, sampling equipment and quality assurance programs.
(f) All licensees or registrants required to meet the additional requirements set forth in this subsection shall establish environmental monitoring programs adequate to determine the impact of their activity on the natural environment around the site of their environmentally significant activity. The established environmental and effluent monitoring program shall address all environmentally significant radionuclide releases and external radiation sources caused or threatened to be caused by the licensee's activities.
(i) Effluent and environmental monitoring results shall include the following minimum information as pertinent:
(A) Information as to flow rates, total volume of effluent, peak concentration, concentration of each radionuclide in the effluent averaged over a period of one year at the point where the effluent leaves a stack, tube, pipe, or similar conduit;
(B) A description of the properties of the effluents, including:
(I) Chemical composition;
(II) Physical characteristics, including suspended solids content in liquid effluents, and nature of gas aerosol for air effluents;
(III) The hydrogen ion concentrations (pH) of liquid effluents; and
(IV) The size range of particulates in effluent released into air;
(C) A description of the anticipated human occupancy in the unrestricted area where the highest concentration of radioactive material from the effluent is expected, and, in the case of a river stream a description of water uses downstream from the point of release of the effluent.
(D) Information as to the highest concentration of each radionuclide in an unrestricted area, including anticipated concentrations averaged over a period of one year:
(I) In air at any point of human occupancy; or
(II) In water at points of use downstream from the point of release of the effluent;
(E) The background concentration of radionuclides in the receiving river or stream prior to the release of liquid effluent;
(F) A description of the waste treatment facilities and procedures used to reduce the concentration of radionuclides in effluents prior to their release;
(G) A written description of sampling techniques and sample analysis methods;
(H) A written description of how all calculated results were obtained from sample analysis data. This explanation shall include example calculations and estimates of the precision and sensitivity of monitoring results;
(I) A written description of the licensee's quality control program including specification of control samples and standard samples used.
(ii) The licensee shall submit in writing to the department within sixty days after January 1 and July 1 of each year, reports specifying the quantities of each of the principle radionuclides released to unrestricted areas in liquid and in gaseous effluent during the previous six months of operations. This data shall be reported in a manner that will permit the department to confirm the potential annual radiation doses to the public. All data from the radiological and nonradiological environmental monitoring program will also be submitted for the same time period and frequency as specified above. The data shall be reported in a manner which will allow the department to confirm the potential annual radiation doses to the public.
(g) For land disposal of radioactive material, the provisions of chapter 246-250 WAC must also be met.
(h) For operation of mineral processing facilities, the provisions of chapter 246-252 WAC must also be met.))
[Statutory Authority: RCW 70.98.050. 98-13-037, § 246-235-080, filed 6/8/98, effective 7/9/98. Statutory Authority: RCW 70.98.050 and 70.98.080. 91-15-112 (Order 184), § 246-235-080, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. 91-02-049 (Order 121), recodified as § 246-235-080, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. 87-01-031 (Order 2450), § 402-22-070, filed 12/11/86; 83-19-050 (Order 2026), § 402-22-070, filed 9/16/83. Statutory Authority: RCW 70.98.050. 81-01-011 (Order 1570), § 402-22-070, filed 12/8/80. Statutory Authority: RCW 70.98.080. 79-12-073 (Order 1459), § 402-22-070, filed 11/30/79, effective 1/1/80. Formerly WAC 402-20-070.]
In addition to the requirements set forth in WAC 246-235-020, a specific license for use of sealed sources in industrial radiography will be issued if:
(1) The applicant submits an adequate program for training radiographers and radiographer's assistants that meets the requirements of WAC 246-243-050 and 246-243-130.
(a) After June 30, 2000, a license applicant need not describe its initial training and examination program for radiographers in the subjects outlined in WAC 246-243-230.
(b) From June 30, 2000, to January 1, 2001, a license applicant may affirm that all individuals acting as industrial radiographers will be certified in radiation safety by a certifying entity before beginning duty as radiographers. This affirmation substitutes for a description of its initial training and examination program for radiographers in the subjects outlined in WAC 246-243-230.
(2) The applicant submits procedures for verifying and documenting the certification status of radiographers and for ensuring that the certification of individuals acting as radiographers remains valid.
(3) The applicant submits written operating and emergency procedures as described in WAC 246-243-140.
(4) The applicant submits a description of a program for inspections of the job performance of each radiographer and radiographers' assistant at intervals not to exceed six months as described in WAC 246-243-050.
(5) The applicant submits a description of the applicant's overall organizational structure as it applies to the radiation safety responsibilities in industrial radiography, including specified delegation of authority and responsibility.
(6) The applicant identifies and lists the qualifications of the individual(s) designated as the RSO (WAC 246-243-047) and potential designees responsible for ensuring that the licensee's radiation safety program is implemented in accordance with approved procedures.
(7) If an applicant intends to perform leak testing of sealed sources or of exposure devices containing depleted uranium (DU) shielding, the applicant shall describe the procedures for performing and the qualifications of the person(s) authorized to do the leak testing. If the applicant intends to analyze its own wipe samples, the application must include a description of the procedures to be followed. The description must include the:
(a) Instruments to be used;
(b) Methods of performing the analysis; and
(c) Pertinent experience of the person who will analyze the wipe samples.
(8) If the applicant intends to perform "in-house" calibrations of survey instruments, the applicant must describe methods to be used and the relevant experience of the person(s) who will perform the calibrations. All calibrations must be performed according to these procedures and the intervals prescribed in WAC 246-243-080.
(9) The applicant identifies and describes the location(s) of all field stations and permanent radiographic installations.
(10) The applicant identifies the location where all records required by this section and other sections of these regulations will be maintained.
[]
In addition to the requirements set forth in WAC 246-235-020, a specific license for any activity within the licensing authority of the department which the department determines will significantly affect the radiological quality of the human environment, including those specified in WAC 197-11-845(1) and 246-03-030 (1)(a)(ii) (i.e., licenses to operate low level waste burial facilities or licenses to operate or expand beyond the design capacity, mineral processing facilities or their tailings areas, whose products, or byproducts, have concentrations of naturally occurring radioactive material in excess of exempt concentrations as specified in WAC 246-232-130, Schedule C), will be issued if the following conditions are met:
(1) Environmental impact statement.
(a) The application for a license or license amendment (other than administrative amendments) is accompanied or preceded by a final environmental impact statement or final declaration of nonsignificance completed in accordance with the State Environmental Policy Act (SEPA) procedures and guidelines specified in chapters 197-11 and 246-03 WAC. For any uranium or thorium mill in operation on or before the effective date of this regulation for which an environmental impact statement has not been prepared previously, an application for license renewal must be accompanied or preceded by a final environmental impact statement or final declaration of nonsignificance completed in accordance with SEPA guidelines.
| Note: | No construction shall be commenced until the license has been issued or unless an emergency exemption from SEPA requirements is granted in accordance with WAC 197-11-880. For the purposes of this subsection, the term "commencement of construction" means any clearing of land, excavation or other substantial action related to a proposed activity for specific licensing that would adversely affect the natural environment of a site; this term does not include changes desirable for the temporary use of the land for public recreational use, limited borings to determine site characteristics as necessary for environmental assessment, or other preconstruction monitoring to establish background information related to suitability of a site or to the protection of environmental values. In the case where an exemption is granted, the applicant shall assume all financial risk for construction activity; waive any claim of entitlement to the issuance of a license based solely upon the grant of the exemption or the commencement of construction pursuant thereto; and furnish, if the circumstances warrant and the department so requires, a financial surety arrangement to insure the protection of the public health, safety and the environment in the event of abandonment, default, or inability of the license applicant to meet the requirements of the act or these regulations. |
(i) Alternative sites to those chosen by the applicant shall include all alternative sites, whether or not those sites are under the control or ownership of the applicant.
(ii) Long term impacts shall include, but not be limited to, decommissioning, decontamination, reclamation impacts and material management associated with the proposed activities.
(iii) Environmental reviews, dose assessments, ecology, construction effects on biota, impact on the environment from the use of chemicals, and socioeconomic effects shall be addressed.
(iv) Alternative disposal sites and techniques for disposal shall be evaluated to determine if a site or technique is clearly superior.
(2) For uranium or thorium milling operations, a bond made payable to the department of health or other acceptable government agency, and in an amount specified by the department, shall be posted to ensure the protection of the public health and safety in the event of abandonment, default or other inability of the licensee to meet the requirements for reclamation and disposal of tailings and for decommissioning the site. The bond, or a copy thereof when the bond is made payable to another government agency, shall be received by the department prior to issuance of the license, or prior to license renewal for mills in operation on or before the effective date of this regulation. Other acceptable surety arrangements in addition to surety bonding include cash deposits, certificates of deposit, deposits of government securities, letters or lines of credit or combinations of the foregoing. The amount and mechanism of the surety arrangement may be reviewed by the department preceding each license renewal and adjustments may be required of the licensee prior to such renewal.
(3) The owner of the proposed uranium or thorium mill and tailings site(s) agrees to transfer or revert to the appropriate state or federal agency upon termination of the license, all lands, buildings and grounds, and any interest therein, necessary to fulfill the purposes of this subsection, except where the lands are held in trust for, or are owned by, any Indian tribe. For any uranium or thorium mill in operation on or before the effective date of this regulation, such an agreement will be required prior to license renewal.
(4) For all uranium and thorium milling operations, the owner or operator shall arrange to pay to the department or its designee a fee in accordance with WAC 246-254-150 for a special security fund for the further maintenance, surveillance or care which may be required after a licensee has ceased to operate.
A minimum fund of two hundred fifty thousand dollars shall be provided by the licensee payable to the state. If a shortfall exists between the amount of money in the special security fund and the two hundred fifty thousand dollars minimum amount, a surety bond, or other acceptable surety instrument as defined above shall be arranged.
(5) The application for a license includes a description of an appropriate program for effluent monitoring, environmental monitoring and data reporting. The description shall encompass locations, frequency, and types of sampling, analytical plans and procedures, minimum detection levels, sampling equipment and quality assurance programs.
(6) All licensees or registrants required to meet the additional requirements set forth in this subsection shall establish environmental monitoring programs adequate to determine the impact of their activity on the natural environment around the site of their environmentally significant activity. The established environmental and effluent monitoring program shall address all environmentally significant radionuclide releases and external radiation sources caused or threatened to be caused by the licensee's activities.
(a) Effluent and environmental monitoring results shall include the following minimum information as pertinent:
(i) Information as to flow rates, total volume of effluent, peak concentration, concentration of each radionuclide in the effluent averaged over a period of one year at the point where the effluent leaves a stack, tube, pipe, or similar conduit;
(ii) A description of the properties of the effluents, including:
(A) Chemical composition;
(B) Physical characteristics, including suspended solids content in liquid effluents, and nature of gas aerosol for air effluents;
(C) The hydrogen ion concentrations (pH) of liquid effluents; and
(D) The size range of particulates in effluent released into air;
(iii) A description of the anticipated human occupancy in the unrestricted area where the highest concentration of radioactive material from the effluent is expected, and, in the case of a river or stream, a description of water uses downstream from the point of release of the effluent.
(iv) Information as to the highest concentration of each radionuclide in an unrestricted area, including anticipated concentrations averaged over a period of one year:
(A) In air at any point of human occupancy; or
(B) In water at points of use downstream from the point of release of the effluent;
(v) The background concentration of radionuclides in the receiving river or stream prior to the release of liquid effluent;
(vi) A description of the waste treatment facilities and procedures used to reduce the concentration of radionuclides in effluents prior to their release;
(vii) A written description of sampling techniques and sample analysis methods;
(viii) A written description of how all calculated results were obtained from sample analysis data. This explanation shall include example calculations and estimates of the precision and sensitivity of monitoring results;
(ix) A written description of the licensee's quality control program including specification of control samples and standard samples used.
(b) The licensee shall submit in writing to the department within sixty days after January 1 and July 1 of each year, reports specifying the quantities of each of the principle radionuclides released to unrestricted areas in liquid and in gaseous effluent during the previous six months of operations. This data shall be reported in a manner that will permit the department to confirm the potential annual radiation doses to the public. All data from the radiological and nonradiological environmental monitoring program will also be submitted for the same time period and frequency as specified above. The data shall be reported in a manner which will allow the department to confirm the potential annual radiation doses to the public.
(7) For land disposal of radioactive material, the provisions of chapter 246-250 WAC must also be met.
(8) For operation of mineral processing facilities, the provisions of chapter 246-252 WAC must also be met.
[]
This section prescribes requirements for the issuance of specific licenses of broad scope for radioactive material ("broad licenses") and certain regulations governing holders of such licenses.*
| *Note: | Authority to transfer possession or control by the manufacturer, processor, or producer of any equipment, device, commodity or other product containing source material or byproduct material whose subsequent possession, use, transfer and disposal by all other persons who are exempted from regulatory requirements may be obtained only from the United States Nuclear Regulatory Commission, Washington, D.C. 20555. |
(a) A "Type A specific license of broad scope" is a specific license authorizing receipt, acquisition, ownership, possession, use and transfer of any chemical or physical form of the radioactive material specified in the license, but not exceeding quantities specified in the license, for any authorized purpose. The quantities specified are usually in the multicurie range.
(b) A "Type B specific license of broad scope" is a specific license authorizing receipt, acquisition, ownership, possession, use and transfer of any chemical or physical form of radioactive material specified in WAC 246-235-140 Schedule B, for any authorized purpose. The possession limit for a Type B broad license, if only one radionuclide is possessed thereunder, is the quantity specified for that radionuclide in WAC 246-235-140 Schedule B, Column I. If two or more radionuclides are possessed thereunder, the possession limit for each is determined as follows: For each radionuclide, determine the ratio of the quantity possessed to the applicable quantity specified in WAC 246-235-140 Schedule B, Column I, for that radionuclide. The sum of the ratios for all radionuclides possessed under the license shall not exceed unity.
(c) A "Type C specific license of broad scope" is a specific license authorizing receipt, acquisition, ownership, possession, use and transfer of any chemical or physical form of radioactive material specified in WAC 246-235-140 Schedule B, for any authorized purpose. The possession limit for a Type C broad license, if only one radionuclide is possessed thereunder, is the quantity specified for that radionuclide in WAC 246-235-140 Schedule B, Column II. If two or more radionuclides are possessed thereunder, the possession limit is determined for each as follows: For each radionuclide determine the ratio of the quantity possessed to the applicable quantity specified in WAC 246-235-140 Schedule B, Column II, for that radionuclide. The sum of the ratios for all radionuclides possessed under the license shall not exceed unity.
(2) An application for a Type A specific license of broad scope will be approved if:
(a) The applicant satisfies the general requirements specified in WAC 246-235-020.
(b) The applicant has engaged in a reasonable number of activities involving the use of radioactive material; and
(c) The applicant has established administrative controls and provisions relating to organization and management, procedures, recordkeeping, material control and accounting, and management review that are necessary to assure safe operations, including:
(i) The establishment of a radiation safety committee composed of such persons as a radiation safety officer, a representative of management, and persons trained and experienced in the safe use of radioactive material;
(ii) The appointment of a radiation safety officer who is qualified by training and experience in radiation protection, and who is available for advice and assistance on radiation safety matters; and
(iii) The establishment of appropriate administrative procedures to assure:
(A) Control of procurement and use of radioactive material;
(B) Completion of safety evaluation of proposed uses of radioactive material which take into consideration such matters as the adequacy of facilities and equipment, training and experience of the user, and the operating or handling procedures; and
(C) Review, approval, and recording by the radiation safety committee of safety evaluation of proposed uses prepared in accordance with item (2)(c)(iii)(B) of this section prior to use of the radioactive material.
(3) An application for a Type B specific license of broad scope will be approved if:
(a) The applicant satisfies the general requirements specified in WAC 246-235-020; and
(b) The applicant has established administrative controls and provisions relating to organization and management, procedures, recordkeeping, material control and accounting, and management review that are necessary to assure safe operations, including:
(i) The appointment of a radiation safety officer who is qualified by training and experience in radiation protection, and who is available for advice and assistance on radiation safety matters; and
(ii) The establishment of appropriate administrative procedures to assure:
(A) Control of procurement and use of radioactive material;
(B) Completion of safety evaluations of proposed uses of radioactive material which take into consideration such matters as the adequacy of facilities and equipment, training and experience of the user, and the operating or handling procedures; and
(C) Review, approval, and recording by the radiation safety officer of safety evaluations of proposed uses prepared in accordance with item (3)(b)(ii)(B) of this section prior to use of the radioactive material.
(4) An application for a Type C specific license of broad scope will be approved if:
(a) The applicant satisfies the general requirements specified in WAC 246-235-020.
(b) The applicant submits a statement that radioactive material will be used only by, or under the direct supervision of individuals, who have received:
(i) A college degree at the bachelor level, or equivalent training and experience, in the physical or biological sciences or in engineering; and
(ii) At least forty hours of training and experience in the safe handling of radioactive material, and in the characteristics of ionizing radiation, units of radiation dose and quantities, radiation detection instrumentation, and biological hazards of exposure to radiation appropriate to the type and forms of radioactive material to be used; and
(c) The applicant has established administrative controls and provisions relating to procurement of radioactive material, procedures, recordkeeping, material control and accounting, and management review necessary to assure safe operations.
(5) Specific licenses of broad scope are subject to the following conditions:
(a) Unless specifically authorized by the department,
persons licensed ((pursuant to)) under this section shall not:
(i) Conduct tracer studies in the environment involving direct release of radioactive material;
(ii) Receive, acquire, own, possess, use or transfer devices containing 100,000 curies or more of radioactive material in sealed sources used for irradiation of materials;
(iii) Conduct activities for which a specific license issued by the department under WAC 246-235-080 through 246-235-086 or WAC 246-235-091 through 246-235-105 is required; or
(iv) Add or cause the addition of radioactive material to any food, beverage, cosmetic, drug or other product designed for ingestion or inhalation by, or application to, a human being.
(b) Each Type A specific license of broad scope issued under this part shall be subject to the condition that radioactive material possessed under the license may only be used by, or under the direct supervision of, individuals approved by the licensee's radiation safety committee.
(c) Each Type B specific license of broad scope issued under this part shall be subject to the condition that radioactive material possessed under the license may only be used by, or under the direct supervision of, individuals approved by the licensee's radiation safety officer.
(d) Each Type C specific license of broad scope issued under this part shall be subject to the condition that radioactive material possessed under the license may only be used by, or under the direct supervision of, individuals who satisfy the requirements of subsection (4) of this section.
[Statutory Authority: RCW 70.98.050. 98-13-037, § 246-235-090, filed 6/8/98, effective 7/9/98. Statutory Authority: RCW 70.98.050 and 70.98.080. 91-15-112 (Order 184), § 246-235-090, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. 91-02-049 (Order 121), recodified as § 246-235-090, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. 79-12-073 (Order 1459), § 402-22-090, filed 11/30/79, effective 1/1/80. Formerly WAC 402-20-073.]
OTS-3598.1
AMENDATORY SECTION(Amending WSR 94-01-073, filed 12/9/93,
effective 1/9/94)
WAC 246-220-007
Statement of philosophy.
In accordance with the recommendations of the Environmental Protection Agency, formerly the Federal Radiation Council, approved by the president of the United States of America, persons engaged in activities under licenses issued by the Washington state department of health pursuant to the Atomic Energy Act of 1954, as amended, shall, in addition to complying with the requirements set forth in chapter 246-221 WAC, make every reasonable effort to maintain radiation exposures, and releases of radioactive materials in effluents to unrestricted areas, as low as is reasonably achievable. Such persons should make particular efforts to keep the radiation exposure of an embryo or fetus as low as is reasonably achievable during the entire gestation period as recommended by the National Council on Radiation Protection and Measurements. The term "as low as is reasonably achievable" means making every reasonable effort to maintain exposures to radiation as far below the dose limits in these regulations as is practical, consistent with the purpose for which the licensed or registered activity is undertaken, taking into account the state of technology, the economics of improvements in relation to the state of technology, the economics of improvements in relation to benefits to the public health and safety, and other societal and socioeconomic considerations, and in relation to the utilization of nuclear energy, ionizing radiation, and radioactive materials in the public interest.
[Statutory Authority: RCW 70.98.050. 94-01-073, § 246-220-007, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. 91-15-112 (Order 184), § 246-220-007, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. 91-02-049 (Order 121), recodified as § 246-220-007, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.050. 81-01-011 (Order 1570), § 402-10-010, filed 12/8/80; Order 1095, § 402-10-010, filed 2/6/76.]
As used in these regulations, these terms have the definitions set forth below. Additional definitions used only in a certain part will be found in that part.
(1) "Absorbed dose" means the energy imparted by ionizing radiation per unit mass of irradiated material. The units of absorbed dose are the gray (Gy) and the rad.
(2) "Accelerator produced material" means any material made radioactive by exposing it in a particle accelerator.
(3) "Act" means Nuclear energy and radiation, chapter 70.98 RCW.
(4) "Activity" means the rate of disintegration or transformation or decay of radioactive material. The units of activity are the becquerel (Bq) and the curie (Ci).
(5) "Adult" means an individual eighteen or more years of age.
(6) "Agreement state" means any state with which the United States Nuclear Regulatory Commission has entered into an effective agreement under section 274 b. of the Atomic Energy Act of 1954, as amended (73 Stat. 689).
(7) "Airborne radioactive material" means any radioactive material dispersed in the air in the form of particulates, dusts, fumes, mists, vapors, or gases.
(8) "Airborne radioactivity area" means a room, enclosure, or operating area in which airborne radioactive material exists in concentrations (a) in excess of the derived air concentration (DAC) specified in WAC 246-221-290, Appendix A, or (b) to such a degree that an individual present in the area without respiratory protective equipment could exceed, during the hours an individual is present in a week, an intake of 0.6 percent of the annual limit on intake (ALI) or twelve DAC-hours.
(9) "Alert" means events may occur, are in progress, or have occurred that could lead to a release of radioactive material but that the release is not expected to require a response by offsite response organizations to protect persons offsite.
(10) "Annual limit on intake" (ALI) means the derived limit for the amount of radioactive material taken into the body of an adult worker by inhalation or ingestion in a year. ALI is the smaller value of intake of a given radionuclide in a year by the reference man that would result in a committed effective dose equivalent of 0.05 Sv (5 rem) or a committed dose equivalent of 0.5 Sv (50 rem) to any individual organ or tissue. ALI values for intake by ingestion and by inhalation of selected radionuclides are given in WAC 246-221-290.
(11) "Background radiation" means radiation from cosmic sources; naturally occurring radioactive materials, including radon, except as a decay product of source or special nuclear material, and including global fallout as it exists in the environment from the testing of nuclear explosive devices or from past nuclear accidents such as Chernobyl that contribute to background radiation and are not under the control of the licensee. "Background radiation" does not include sources of radiation from radioactive materials regulated by the department.
(12) "Becquerel" (Bq) means the SI unit of activity. One becquerel is equal to 1 disintegration or transformation per second (s-1).
(13) "Bioassay" means the determination of kinds, quantities or concentrations, and, in some cases, the locations of radioactive material in the human body, whether by direct measurement, in vivo counting, or by analysis and evaluation of materials excreted or removed from the human body. For purposes of these regulations, "radiobioassay" is an equivalent term.
(14) "Byproduct material" means: (a) Any radioactive material (except special nuclear material) yielded in or made radioactive by exposure to the radiation incident to the process of producing or utilizing special nuclear material, and (b) the tailings or wastes produced by the extraction or concentration of uranium or thorium from any ore processed primarily for its source material content, including discrete surface wastes resulting from uranium or thorium solution extraction processes. Underground ore bodies depleted by these solution extraction operations do not constitute "byproduct material" within this definition.
(15) "Calendar quarter" means not less than twelve consecutive weeks nor more than fourteen consecutive weeks. The first calendar quarter of each year shall begin in January and subsequent calendar quarters shall be so arranged such that no day is included in more than one calendar quarter and no day in any one year is omitted from inclusion within a calendar quarter. No licensee or registrant shall change the method of determining calendar quarters for purposes of these regulations except at the beginning of a calendar year.
(16) "Calibration" means the determination of (a) the response or reading of an instrument relative to a series of known radiation values over the range of the instrument, or (b) the strength of a source of radiation relative to a standard.
(17) "CFR" means Code of Federal Regulations.
(18) "Class" means a classification scheme for inhaled material according to its rate of clearance from the pulmonary region of the lung. Materials are classified as D, W, or Y, which applies to a range of clearance half-times: For Class D, Days, of less than ten days, for Class W, Weeks, from ten to one hundred days, and for Class Y, Years, of greater than one hundred days. For purposes of these regulations, "lung class" and "inhalation class" are equivalent terms. For "class of waste" see WAC 246-249-040.
(19) "Collective dose" means the sum of the individual doses received in a given period of time by a specified population from exposure to a specified source of radiation.
(20) "Committed dose equivalent" (HT,50) means the dose equivalent to organs or tissues of reference (T) that will be received from an intake of radioactive material by an individual during the fifty-year period following the intake.
(21) "Committed effective dose equivalent" (HE,50) is the sum of the products of the weighting factors applicable to each of the body organs or tissues that are irradiated and the committed dose equivalent to each of these organs or tissues (HE,50= &Sgr; wT,HT,50).
(22) "Constraint" or dose constraint means a value above which specified licensee actions are required.
(23) "Controlled area." See "Restricted area."
(24) "Curie" means a unit of quantity of radioactivity. One curie (Ci) is that quantity of radioactive material which decays at the rate of 3.7 x 1010 transformations per second (tps).
(25) "Declared pregnant woman" means a woman who has voluntarily informed her employer, in writing, of her pregnancy, and her estimated date of conception.
(26) "Deep dose equivalent" (Hd), which applies to external whole body exposure, means the dose equivalent at a tissue depth of 1 centimeter (1000 mg/cm2).
(27) "Department" means the department of health, division of radiation protection, which has been designated as the state radiation control agency.
(28) "Depleted uranium" means the source material uranium in which the isotope Uranium-235 is less than 0.711 percent by weight of the total uranium present. Depleted uranium does not include special nuclear material.
(29) "Derived air concentration" (DAC) means the concentration of a given radionuclide in air which, if breathed by the reference man for a working year of two thousand hours under conditions of light work, results in an intake of one ALI. For purposes of these regulations, the condition of light work is an inhalation rate of 1.2 cubic meters of air per hour for two thousand hours in a year. DAC values are given in WAC 246-221-290.
(30) "Derived air concentration-hour" (DAC-hour) means the product of the concentration of radioactive material in air, expressed as a fraction or multiple of the derived air concentration for each radionuclide, and the time of exposure to that radionuclide, in hours. A licensee or registrant may take two thousand DAC-hours to represent one ALI, equivalent to a committed effective dose equivalent of 0.05 Sv (5 rem).
(31) "Dose" is a generic term that means absorbed dose, dose equivalent, effective dose equivalent, committed dose equivalent, committed effective dose equivalent, total organ dose equivalent, or total effective dose equivalent. For purposes of these regulations, "radiation dose" is an equivalent term.
(32) "Dose commitment" means the total radiation dose to a part of the body that will result from retention in the body of radioactive material. For purposes of estimating the dose commitment, it is assumed that from the time of intake the period of exposure to retained material will not exceed fifty years.
(33) "Dose equivalent (HT)" means the product of the absorbed dose in tissue, quality factor, and all other necessary modifying factors at the location of interest. The units of dose equivalent are the sievert (Sv) and rem.
(34) "Dose limits" means the permissible upper bounds of radiation doses established in accordance with these regulations. For purposes of these regulations, "limits" is an equivalent term.
(35) "Dosimetry processor" means a person that processes and evaluates individual monitoring devices in order to determine the radiation dose delivered to the monitoring devices.
(36) "dpm" means disintegrations per minute. See also "curie."
(37) "Effective dose equivalent (HE)" means the sum of the products of the dose equivalent to each organ or tissue (HT) and the weighting factor (wT) applicable to each of the body organs or tissues that are irradiated (HE= &Sgr; wTHT).
(38) "Embryo/fetus" means the developing human organism from conception until the time of birth.
(39) "Entrance or access point" means any opening through which an individual or extremity of an individual could gain access to radiation areas or to licensed radioactive materials. This includes entry or exit portals of sufficient size to permit human entry, without respect to their intended use.
(40) "Exposure" means (a), when used as a verb, being exposed to ionizing radiation or to radioactive material, or (b), when used as a noun, the quotient of &Dgr;Q by &Dgr;m where "&Dgr;Q" is the absolute value of the total charge of the ions of one sign produced in air when all the electrons (negatrons and positrons) liberated by photons in a volume element of air having mass "&Dgr;m" are completely stopped in air. The special unit of exposure is the roentgen (R) and the SI equivalent is the coulomb per kilogram. One roentgen is equal to 2.58 x 10-4 coulomb per kilogram of air.
(41) "Exposure rate" means the exposure per unit of time, such as roentgen per minute and milliroentgen per hour.
(42) "External dose" means that portion of the dose equivalent received from any source of radiation outside the body.
(43) "Extremity" means hand, elbow, arm below the elbow, foot, knee, and leg below the knee.
(44) "Eye dose equivalent" means the external dose equivalent to the lens of the eye at a tissue depth of 0.3 centimeter (300 mg/cm2).
(45) "Former United States Atomic Energy Commission (AEC) or United States Nuclear Regulatory Commission (NRC) licensed facilities" means nuclear reactors, nuclear fuel reprocessing plants, uranium enrichment plants, or critical mass experimental facilities where AEC or NRC licenses have been terminated.
(46) "Generally applicable environmental radiation standards" means standards issued by the United States Environmental Protection Agency (EPA) under the authority of the Atomic Energy Act of 1954, as amended, that impose limits on radiation exposures or levels, or concentrations or quantities of radioactive material, in the general environment outside the boundaries of locations under the control of persons possessing or using radioactive material.
(47) "Gray" (Gy) means the SI unit of absorbed dose. One gray is equal to an absorbed dose of 1 joule/kilogram (100 rad).
(48) "Healing arts" means the disciplines of medicine, dentistry, osteopathy, chiropractic, podiatry, and veterinary medicine.
(49) "High radiation area" means any area, accessible to individuals, in which radiation levels could result in an individual receiving a dose equivalent in excess of 1 mSv (0.1 rem) in one hour at 30 centimeters from any source of radiation or from any surface that the radiation penetrates. For purposes of these regulations, rooms or areas in which diagnostic x-ray systems are used for healing arts purposes are not considered high radiation areas.
(50) "Human use" means the intentional internal or external administration of radiation or radioactive material to human beings.
(51) "Immediate" or "immediately" means as soon as possible but no later than four hours after the initiating condition.
(52) "IND" means investigatory new drug for which an exemption has been claimed under the United States Food, Drug and Cosmetic Act (Title 21 CFR).
(53) "Individual" means any human being.
(54) "Individual monitoring" means the assessment of:
(a) Dose equivalent (i) by the use of individual monitoring devices or (ii) by the use of survey data; or
(b) Committed effective dose equivalent (i) by bioassay or (ii) by determination of the time-weighted air concentrations to which an individual has been exposed, that is, DAC-hours.
(55) "Individual monitoring devices" means devices designed to be worn by a single individual for the assessment of dose equivalent. For purposes of these regulations, individual monitoring equipment, personnel monitoring device, personnel dosimeter, and dosimeter are equivalent terms. Examples of individual monitoring devices are film badges, thermoluminescent dosimeters (TLDs), pocket ionization chambers, and personal air sampling devices.
(56) "Inspection" means an official examination or observation by the department including but not limited to, tests, surveys, and monitoring to determine compliance with rules, regulations, orders, requirements and conditions of the department.
(57) "Interlock" means a device arranged or connected such that the occurrence of an event or condition is required before a second event or condition can occur or continue to occur.
(58) "Internal dose" means that portion of the dose equivalent received from radioactive material taken into the body.
(59) "Irretrievable source" means any sealed source containing licensed material which is pulled off or not connected to the wireline downhole and for which all reasonable effort at recovery, as determined by the department, has been expended.
(60) "License" means a license issued by the department in accordance with the regulations adopted by the department.
(61) "Licensed material" means radioactive material received, possessed, used, transferred, or disposed under a general or specific license issued by the department.
(62) "Licensee" means any person who is licensed by the department in accordance with these regulations and the act.
(63) "Licensing state" means any state with regulations equivalent to the suggested state regulations for control of radiation relating to, and an effective program for, the regulatory control of NARM and which has been granted final designation by the Conference of Radiation Control Program Directors, Inc.
(64) "Lost or missing licensed material" means licensed material whose location is unknown. This definition includes licensed material that has been shipped but has not reached its planned destination and whose location cannot be readily traced in the transportation system.
(65) "Member of the public" means an individual except when the individual is receiving an occupational dose.
(66) "Minor" means an individual less than eighteen years of age.
(67) "Monitoring" means the measurement of radiation, radioactive material concentrations, surface area activities or quantities of radioactive material and the use of the results of these measurements to evaluate potential exposures and doses. For purposes of these regulations, radiation monitoring and radiation protection monitoring are equivalent terms.
(68) "NARM" means any naturally occurring or accelerator-produced radioactive material. It does not include by-product, source, or special nuclear material. For the purpose of meeting the definition of a Licensing State by the Conference of Radiation Control Program Directors, Inc. (CRCPD), NARM refers only to discrete sources of NARM. Diffuse sources of NARM are excluded from consideration by the CRCPD for Licensing State designation purposes.
(69) "Natural radioactivity" means radioactivity of naturally occurring nuclides.
(70) "NDA" means a new drug application which has been submitted to the United States Food and Drug Administration.
(71) "Nonstochastic effect" means a health effect, the severity of which varies with the dose and for which a threshold is believed to exist. Radiation-induced cataract formation is an example of a nonstochastic effect. For purposes of these regulations, a "deterministic effect" is an equivalent term.
(72) "Nuclear Regulatory Commission" (NRC) means the United States Nuclear Regulatory Commission or its duly authorized representatives.
(73) "Occupational dose" means the dose received by an individual in the course of employment in which the individual's assigned duties involve exposure to radiation or to radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee, registrant, or other person. Occupational dose does not include dose received: From background radiation, from any medical administration the individual has received, from exposure to individuals administered radioactive material and released pursuant to chapters 246-239 and 246-240 WAC, from voluntary participation in medical research programs, or as a member of the public.
(74) "Ore refineries" means all processors of a radioactive material ore.
(75) "Particle accelerator" means any machine capable of accelerating electrons, protons, deuterons, or other charged particles in a vacuum and of discharging the resultant particulate or other radiation into a medium at energies usually in excess of 1 MeV.
(76) "Permittee" means a person who has applied for, and received, a valid site use permit for use of the low-level waste disposal facility at Hanford, Washington.
(77) "Person" means any individual, corporation, partnership, firm, association, trust, estate, public or private institution, group, agency, political subdivision of this state, any other state or political subdivision or agency thereof, and any legal successor, representative, agent or agency of the foregoing, but shall not include federal government agencies.
(78) "Personal supervision" means supervision such that the supervisor is physically present at the facility and in such proximity that contact can be maintained and immediate assistance given as required.
(79) "Personnel monitoring equipment." See individual monitoring devices.
(80) "Pharmacist" means an individual licensed by this state to compound and dispense drugs, and poisons.
(81) "Physician" means an individual licensed by this state to prescribe and dispense drugs in the practice of medicine.
(82) "Planned special exposure" means an infrequent exposure to radiation, separate from and in addition to the annual occupational dose limits.
(83) "Practitioner" means an individual licensed by the state in the practice of a healing art (i.e., physician, dentist, podiatrist, chiropractor, etc.).
(84) "Public dose" means the dose received by a member of the public from exposure to sources of radiation under the licensee's or registrant's control or to radiation or radioactive material released by the licensee. Public dose does not include occupational dose or doses received from background radiation, from any medical administration the individual has received, from exposure to individuals administered radioactive material and released pursuant to chapters 246-239 and 246-240 WAC, or from voluntary participation in medical research programs.
(85) "Qualified expert" means an individual who has demonstrated to the satisfaction of the department he/she has the knowledge, training, and experience to measure ionizing radiation, to evaluate safety techniques, and to advise regarding radiation protection needs. The department reserves the right to recognize the qualifications of an individual in specific areas of radiation protection.
(86) "Quality factor" (Q) means the modifying factor, listed in Tables I and II, that is used to derive dose equivalent from absorbed dose.
| TABLE I | ||
| QUALITY FACTORS AND ABSORBED DOSE EQUIVALENCIES | ||
TYPE OF RADIATION |
Quality Factor (Q) |
Absorbed Dose
Equal to A Unit Dose Equivalenta |
| X, gamma, or beta radiation and high-speed electrons |
1 | 1 |
| Alpha particles, multiple- charged particles, fission fragments and heavy particles of unknown charge |
20 | 0.05 |
| Neutrons of unknown energy | 10 | 0.1 |
| High-energy protons | 10 | 0.1 |
a
Absorbed dose in rad equal to 1 rem or the absorbed dose in gray equal to 1 Sv.
If it is more convenient to measure the neutron fluence rate
rather than to determine the neutron dose equivalent rate in
sievert per hour or rem per hour as required for Table I, then
0.01 Sv (1 rem) of neutron radiation of unknown energies may, for
purposes of these regulations, be assumed to result from a total
fluence of 25 million neutrons per square centimeter incident
upon the body. If sufficient information exists to estimate the
approximate energy distribution of the neutrons, the licensee or
registrant may use the fluence rate per unit dose equivalent or
the appropriate Q value from Table II to convert a measured
tissue dose in gray or rad to dose equivalent in sievert or rem.
| TABLE II |
|||
| MEAN QUALITY FACTORS, Q, AND FLUENCE PER UNIT DOSE EQUIVALENT FOR MONOENERGETIC NEUTRONS |
|||
| Neutron Energy (MeV) |
Quality Factora (Q) |
Fluence per Unit Dose Equivalentb (neutrons cm-2 rem-1) |
Fluence per Unit Dose Equivalentb (neutrons cm-2 Sv-1) |
| (thermal)2.5 x 10-8 | 2 | 980 x 106 | 980 x 108 |
| 1 x 10-7 | 2 | 980 x 106 | 980 x 108 |
| 1 x 10-6 | 2 | 810 x 106 | 810 x 108 |
| 1 x 10-5 | 2 | 810 x 106 | 810 x 108 |
| 1 x 10-4 | 2 | 840 x 106 | 840 x 108 |
| 1 x 10-3 | 2 | 980 x 106 | 980 x 108 |
| 1 x 10-2 | 2.5 | 1010 x 106 | 1010 x 108 |
| 1 x 10-1 | 7.5 | 170 x 106 | 170 x 108 |
| 5 x 10-1 | 11 | 39 x 106 | 39 x 108 |
| 1 | 11 | 27 x 106 | 27 x 108 |
| 2.5 | 9 | 29 x 106 | 29 x 108 |
| 5 | 8 | 23 x 106 | 23 x 108 |
| 7 | 7 | 24 x 106 | 24 x 108 |
| 10 | 6.5 | 24 x 106 | 24 x 108 |
| 14 | 7.5 | 17 x 106 | 17 x 108 |
| 20 | 8 | 16 x 106 | 16 x 108 |
| 40 | 7 | 14 x 106 | 14 x 108 |
| 60 | 5.5 | 16 x 106 | 16 x 108 |
| 1 x 102 | 4 | 20 x 106 | 20 x 108 |
| 2 x 102 | 3.5 | 19 x 106 | 19 x 108 |
| 3 x 102 | 3.5 | 16 x 106 | 16 x 108 |
| 4 x 102 | 3.5 | 14 x 106 | 14 x 108 |
a
Value of quality factor (Q) at the point where the dose equivalent is maximum in a 30-cm diameter cylinder
tissue-equivalent phantom.
b
Monoenergetic neutrons incident normally on a 30-cm diameter cylinder tissue-equivalent phantom.
(87) "Quarter" means a period of time equal to one-fourth of the year observed by the licensee, approximately thirteen consecutive weeks, providing that the beginning of the first quarter in a year coincides with the starting date of the year and that no day is omitted or duplicated in consecutive quarters.
(88) "Rad" means the special unit of absorbed dose. One rad equals one-hundredth of a joule per kilogram of material; for example, if tissue is the material of interest, then 1 rad equals 100 ergs per gram of tissue. One rad is equal to an absorbed dose of 100 erg/gram or 0.01 joule/kilogram (0.01 gray).
(89) "Radiation" means alpha particles, beta particles, gamma rays, x-rays, neutrons, high-speed electrons, high-speed protons, and other particles capable of producing ions. For purposes of these regulations, ionizing radiation is an equivalent term. Radiation, as used in these regulations, does not include magnetic fields or nonionizing radiation, such as radiowaves or microwaves, visible, infrared, or ultraviolet light.
(90) "Radiation area" means any area, accessible to individuals, in which radiation levels could result in an individual receiving a dose equivalent in excess of 0.05 mSv (0.005 rem) in one hour at thirty centimeters from the source of radiation or from any surface that the radiation penetrates.
(91) "Radiation machine" means any device capable of producing ionizing radiation except those devices with radioactive materials as the only source of radiation.
(92) "Radiation safety officer" means an individual who has the knowledge and responsibility to apply appropriate radiation protection regulations and has been assigned such responsibility by the licensee or registrant.
(93) "Radiation source." See "Source of radiation."
(94) "Radioactive material" means any material (solid, liquid, or gas) which emits radiation spontaneously.
(95) "Radioactive waste" means any radioactive material which is no longer of use and intended for disposal or treatment for the purposes of disposal.
(96) "Radioactivity" means the transformation of unstable atomic nuclei by the emission of radiation.
(97) "Reference man" means a hypothetical aggregation of human physical and physiological characteristics determined by international consensus. These characteristics may be used by researchers and public health workers to standardize results of experiments and to relate biological insult to a common base.
(98) "Registrable item" means any radiation machine except those exempted by RCW 70.98.180 or exempted by the department pursuant to the authority of RCW 70.98.080.
(99) "Registrant" means any person who is registered by the department or is legally obligated to register with the department in accordance with these regulations and the act.
(100) "Registration" means registration with the department in accordance with the regulations adopted by the department.
(101) "Regulations of the United States Department of Transportation" means the regulations in 49 CFR Parts 170-189, 14 CFR Part 103, and 46 CFR Part 146.
(102) "Rem" means the special unit of any of the quantities expressed as dose equivalent. The dose equivalent in rem is equal to the absorbed dose in rad multiplied by the quality factor (1 rem= 0.01 Sv).
(103) "Research and development" means: (a) Theoretical analysis, exploration, or experimentation; or (b) the extension of investigative findings and theories of a scientific or technical nature into practical application for experimental and demonstration purposes, including the experimental production and testing of models, devices, equipment, materials, and processes. Research and development does not include the internal or external administration of radiation or radioactive material to human beings.
(104) "Respiratory protective equipment" means an apparatus, such as a respirator, used to reduce an individual's intake of airborne radioactive materials.
(105) "Restricted area" means any area to which access is limited by the licensee or registrant for purposes of protecting individuals against undue risks from exposure to radiation and radioactive material. "Restricted area" shall not include any areas used for residential quarters, although a separate room or rooms in a residential building may be set apart as a restricted area.
(106) "Roentgen" (R) means the special unit of exposure. One roentgen equals 2.58 x 10-4 coulombs/kilogram of air.
(107) "Sanitary sewerage" means a system of public sewers for carrying off waste water and refuse, but excluding sewage treatment facilities, septic tanks, and leach fields owned or operated by the licensee or registrant.
(108) "Sealed source" means any ((device containing))
radioactive material ((to be used as a source of radiation which
has been constructed in such a manner as)) that is encased in a
capsule designed to prevent leakage or the escape of ((any)) the
radioactive material.
(109) "Shallow dose equivalent" (Hs), which applies to the external exposure of the skin or an extremity, means the dose equivalent at a tissue depth of 0.007 centimeter (7 mg/cm2) averaged over an area of 1 square centimeter.
(110) "SI" means an abbreviation of the International System of Units.
(111) "Sievert" means the SI unit of any of the quantities expressed as dose equivalent. The dose equivalent in sievert is equal to the absorbed dose in gray multiplied by the quality factor (1 Sv= 100 rem).
(112) "Site area emergency" means events may occur, are in progress, or have occurred that could lead to a significant release of radioactive material and that could require a response by offsite response organizations to protect persons offsite.
(113) "Site boundary" means that line beyond which the land or property is not owned, leased, or otherwise controlled by the licensee or registrant.
(114) "Source container" means a device in which radioactive material is transported or stored.
(115) "Source material" means: (a) Uranium or thorium, or any combination thereof, in any physical or chemical form, or (b) ores which contain by weight one-twentieth of one percent (0.05 percent) or more of (i) uranium, (ii) thorium, or (iii) any combination thereof. Source material does not include special nuclear material.
(116) "Source material milling" means the extraction or concentration of uranium or thorium from any ore processing primarily for its source material content.
(117) "Source of radiation" means any radioactive material, or any device or equipment emitting or capable of producing ionizing radiation.
(118) "Special nuclear material" means:
(a) Plutonium, uranium-233, uranium enriched in the isotope 233 or in the isotope 235, and any other material that the United States Nuclear Regulatory Commission, pursuant to the provisions of section 51 of the Atomic Energy Act of 1954, as amended, determines to be special nuclear material, but does not include source material; or
(b) Any material artificially enriched in any of the foregoing, but does not include source material.
(119) "Special nuclear material in quantities not sufficient to form a critical mass" means uranium enriched in the isotope U-235 in quantities not exceeding three hundred fifty grams of contained U-235; Uranium-233 in quantities not exceeding two hundred grams; Plutonium in quantities not exceeding two hundred grams; or any combination of them in accordance with the following formula: For each kind of special nuclear material, determine the ratio between the quantity of that special nuclear material and the quantity specified above for the same kind of special nuclear material. The sum of such ratios for all of the kinds of special nuclear material in combination shall not exceed "1" (i.e., unity). For example, the following quantities in combination would not exceed the limitation and are within the formula:
| 175(grams contained U-235) 350 |
+ | ||
| 50(grams U-233) 200 |
+ | ||
| 50(grams Pu) 200 |
< 1 | ||
(121) "Survey" means an evaluation of the radiological conditions and potential hazards incident to the production, use, release, disposal, or presence of sources of radiation. When appropriate, such evaluation includes, but is not limited to, tests, physical examinations, calculations and measurements of levels of radiation or concentration of radioactive material present.
(122) "Test" means (a) the process of verifying compliance with an applicable regulation, or (b) a method for determining the characteristics or condition of sources of radiation or components thereof.
(123) "These regulations" mean all parts of the rules for radiation protection of the state of Washington.
(124) "Total effective dose equivalent" (TEDE) means the sum of the deep dose equivalent for external exposures and the committed effective dose equivalent for internal exposures.
(125) "Total organ dose equivalent (TODE)" means the sum of the deep dose equivalent and the committed dose equivalent to the organ or tissue receiving the highest dose.
(126) "United States Department of Energy" means the Department of Energy established by Public Law 95-91, August 4, 1977, 91 Stat. 565, 42 U.S.C. 7101 et seq., to the extent that the department exercises functions formerly vested in the United States Atomic Energy Commission, its chairman, members, officers and components and transferred to the United States Energy Research and Development Administration and to the administrator thereof pursuant to sections 104 (b), (c) and (d) of the Energy Reorganization Act of 1974 (Public Law 93-438, October 11, 1974, 88 Stat. 1233 at 1237, 42 U.S.C. 5814 effective January 19, 1975) and retransferred to the Secretary of Energy pursuant to section 301(a) of the Department of Energy Organization Act (Public Law 95-91, August 4, 1977, 91 Stat. 565 at 577-578, 42 U.S.C. 7151, effective October 1, 1977).
(127) "Unrefined and unprocessed ore" means ore in its natural form prior to any processing, such as grinding, roasting, beneficiating, or refining.
(128) "Unrestricted area" (uncontrolled area) means any area which is not a restricted area. Areas where the external dose exceeds 2 mrem in any one hour or where the public dose, taking into account occupancy factors, will exceed 100 mrem total effective dose equivalent in any one year must be restricted.
(129) "Very high radiation area" means an area, accessible to individuals, in which radiation levels could result in an individual receiving an absorbed dose in excess of 5 Gy (500 rad) in one hour at one meter from a source of radiation or from any surface that the radiation penetrates.
(130) "Waste handling licensees" mean persons licensed to receive and store radioactive wastes prior to disposal and/or persons licensed to dispose of radioactive waste.
(131) "Week" means seven consecutive days starting on Sunday.
(132) "Weighting factor" wT for an organ or tissue (T) means the proportion of the risk of stochastic effects resulting from irradiation of that organ or tissue to the total risk of stochastic effects when the whole body is irradiated uniformly. For calculating the effective dose equivalent, the values of wT are:
| ORGAN DOSE WEIGHTING FACTORS | |||
| Organ or Tissue |
wT |
||
Gonads |
0.25 |
||
| Breast | 0.15 | ||
| Red bone marrow | 0.12 | ||
| Lung | 0.12 | ||
| Thyroid | 0.03 | ||
| Bone surfaces | 0.03 | ||
| Remainder | 0.30a |
||
| Whole Body | 1.00b | ||
a
0.30 results form 0.06 for each of 5 "remainder” organs, excluding the skin and the lens of the eye, that receive the highest
doses.
b
For the purpose of weighting the external whole body dose, for adding it to the internal dose, a single weighting factor,
wT=1.0, has been specified. The use of other weighting factors for external exposure will be approved on a case-by-case
basis until such time as specific guidance is issued.
(133) "Whole body" means, for purposes of external exposure, head, trunk including male gonads, arms above the elbow, or legs above the knee.
(134) "Worker" means an individual engaged in activities under a license or registration issued by the department and controlled by a licensee or registrant but does not include the licensee or registrant. Where the licensee or registrant is an individual rather than one of the other legal entities defined under "person," the radiation exposure limits for the worker also apply to the individual who is the licensee or registrant. If students of age eighteen years or older are subjected routinely to work involving radiation, then the students are considered to be workers. Individuals of less than eighteen years of age shall meet the requirements of WAC 246-221-050.
(135) "Working level" (WL) means any combination of short-lived radon daughters in 1 liter of air that will result in the ultimate emission of 1.3 x 105 MeV of potential alpha particle energy. The short-lived radon daughters are -- for radon-222: polonium-218, lead-214, bismuth-214, and polonium-214; and for radon-220: polonium-216, lead-212, bismuth-212, and polonium-212.
(136) "Working level month" (WLM) means an exposure to one working level for one hundred seventy hours -- two thousand working hours per year divided by twelve months per year is approximately equal to one hundred seventy hours per month.
(137) "Year" means the period of time beginning in January used to determine compliance with the provisions of these regulations. The licensee or registrant may change the starting date of the year used to determine compliance by the licensee or registrant provided that the change is made at the beginning of the year and that no day is omitted or duplicated in consecutive years.
[Statutory Authority: RCW 70.98.050. 99-15-105, § 246-220-010, filed 7/21/99, effective 8/21/99; 98-13-037, § 246-220-010, filed 6/8/98, effective 7/9/98; 95-01-108, § 246-220-010, filed 12/21/94, effective 1/21/95; 94-01-073, § 246-220-010, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. 91-15-112 (Order 184), § 246-220-010, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. 91-02-049 (Order 121), recodified as § 246-220-010, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. 87-01-031 (Order 2450), § 402-12-050, filed 12/11/86; 83-19-050 (Order 2026), § 402-12-050, filed 9/16/83. Statutory Authority: Chapter 70.121 RCW. 81-16-031 (Order 1683), § 402-12-050, filed 7/28/81. Statutory Authority: RCW 70.98.050. 81-01-011 (Order 1570), § 402-12-050, filed 12/8/80; Order 1095, § 402-12-050, filed 2/6/76; Order 708, § 402-12-050, filed 8/24/72; Order 1, § 402-12-050, filed 7/2/71; Order 1, § 402-12-050, filed 1/8/69; Rules (part), filed 10/26/66.]
OTS-3599.1
AMENDATORY SECTION(Amending WSR 94-01-073, filed 12/9/93,
effective 1/9/94)
WAC 246-221-020
Determination of prior occupational dose.
(1) For each individual who ((may enter the licensee's or
registrant's restricted area and)) is likely to receive, in a
year, an occupational dose requiring monitoring pursuant to WAC 246-221-090 and 246-221-100, the licensee or registrant shall:
(a) Determine the occupational radiation dose received during the current year; and
(b) Attempt to obtain the records of lifetime cumulative occupational radiation dose.
(2) Prior to permitting an individual to participate in a planned special exposure, the licensee or registrant shall determine:
(a) The internal and external doses from all previous planned special exposures; and
(b) All doses in excess of the limits, including doses received during accidents and emergencies, received during the lifetime of the individual.
(3) In complying with the requirements of subsection (1) of this section, a licensee or registrant may:
(a) Accept, as a record of the occupational dose that the individual received during the current year, a written signed statement from the individual, or from the individual's most recent employer for work involving radiation exposure, that discloses the nature and the amount of any occupational dose that the individual received during the current year; and
(b) Accept, as the record of lifetime cumulative radiation dose, an up-to-date Form RHF-4A, or equivalent, signed by the individual and countersigned by an appropriate official of the most recent employer for work involving radiation exposure, or the individual's current employer, if the individual is not employed by the licensee or registrant; and
(c) Obtain reports of the individual's dose equivalent from the most recent employer for work involving radiation exposure, or the individual's current employer, if the individual is not employed by the licensee or registrant, by telephone, telegram, facsimile, or letter. The licensee or registrant shall request a written verification of the dose data if the authenticity of the transmitted report cannot be established.
(4) The licensee or registrant shall record the exposure history, as required by subsection (1) of this section, on Form RHF-4A, or other clear and legible record, of all the information required on that form. The form or record shall show each period in which the individual received occupational exposure to radiation or radioactive material and shall be signed by the individual who received the exposure. For each period for which the licensee or registrant obtains reports, the licensee or registrant shall use the dose shown in the report in preparing Form RHF-4A. For any period in which the licensee or registrant does not obtain a report, the licensee or registrant shall place a notation on Form RHF-4A indicating the periods of time for which data are not available.
(5) Licensees or registrants are not required to reevaluate the separate external dose equivalents and internal committed dose equivalents or intakes of radionuclides assessed under the regulations in effect before January 1, 1994. Further, occupational exposure histories obtained and recorded on Form RHF-4 before January 1, 1994, would not have included effective dose equivalent, but may be used in the absence of specific information on the intake of radionuclides by the individual.
(6) If the licensee or registrant is unable to obtain a complete record of an individual's current and previously accumulated occupational dose, the licensee or registrant shall assume:
(a) In establishing administrative controls under WAC 246-221-010(6) for the current year, that the allowable dose limit for the individual is reduced by 12.5 mSv (1.25 rem) for each calendar quarter for which records were unavailable and the individual was engaged in activities that could have resulted in occupational radiation exposure; and
(b) That the individual is not available for planned special exposures.
(7) The licensee or registrant shall retain the records on Form RHF-4A or equivalent until the department terminates each pertinent license requiring this record. The licensee or registrant shall retain records used in preparing Form RHF-4 or RHF-4A for three years after the record is made.
[Statutory Authority: RCW 70.98.050. 94-01-073, § 246-221-020, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. 91-15-112 (Order 184), § 246-221-020, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. 91-02-049 (Order 121), recodified as § 246-221-020, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.050. 81-01-011 (Order 1570), § 402-24-024, filed 12/8/80; Order 1095, § 402-24-024, filed 2/6/76.]
OTS-3600.3
AMENDATORY SECTION(Amending WSR 94-01-073, filed 12/9/93,
effective 1/9/94)
WAC 246-243-020
Definitions.
As used in this part:
(1) (("Enclosed radiography" means industrial radiography
employing radiographic exposure devices conducted in an enclosed
cabinet or room and includes cabinet radiography and shielded
room radiography.
(a) "Cabinet radiography" means industrial radiography employing radiographic exposure devices conducted in an enclosure or cabinet so shielded that every location at the exterior meets the conditions specified in WAC 246-221-060 of these regulations.
(b) "Shielded-room radiography" means industrial radiography conducted in a room so shielded that every location on the exterior meets the conditions specified in WAC 246-221-060 of these regulations.
(2))) "Annual refresher safety training" means a review conducted or provided by the licensee for its employees on radiation safety aspects of industrial radiography. The review may include, as appropriate, the results of internal inspections, new procedures or equipment, new or revised regulations, accidents or errors that have been observed, and should also provide opportunities for employees to ask safety questions.
(2) "Associated equipment" means equipment that is used in conjunction with a radiographic exposure device to make radiographic exposures that drives, guides, or comes in contact with the source, (e.g., guide tube, control tube, control (drive) cable, removable source stop, "J" tube and collimator) when it is used as an exposure head.
(3) "Certifying entity" means an independent certifying organization meeting the requirements in WAC 246-243-250 Appendix C or an agreement state meeting the requirements in WAC 246-243-250 Appendix C, subsections (2) and (3).
(4) "Collimator" means a radiation shield that is placed on the end of the guide tube or directly onto a radiographic exposure device to restrict the size of the radiation beam when the sealed source is cranked into position to make a radiographic exposure.
(5) "Control (drive) cable" means the cable that is connected to the source assembly and used to drive the source to and from the exposure location.
(6) "Control drive mechanism" means a device that enables the source assembly to be moved to and from the exposure device.
(7) "Control tube" means a protective sheath for guiding the control cable. The control tube connects the control drive mechanism to the radiographic exposure device.
(8) "Exposure head" means a device that locates the gamma radiography sealed source in the selected working position. (An exposure head is also known as a source stop.)
(9) "Field station" means a facility where licensed material may be stored or used and from which equipment is dispatched.
(10) "Guide tube (projection sheath)" means a flexible or rigid tube (i.e., "J" tube) for guiding the source assembly and the attached control cable from the exposure device to the exposure head. The guide tube may also include the connections necessary for attachment to the exposure device and to the exposure head.
(11) "Hands-on experience" means experience in all of those areas considered to be directly involved in the radiography process.
(12) "Independent certifying organization" means an independent organization that meets all of the criteria of WAC 246-243-250 Appendix C.
(13) "Industrial radiography" (radiography) means the examination of the macroscopic structure of materials by nondestructive methods utilizing sources of radiation to make radiographic images. Industrial radiography as used in this chapter does not include well logging operations.
(((3))) (14) "Lay-barge radiography" means industrial
radiography performed on any water vessel used for laying pipe.
(15) "Offshore platform radiography" means industrial radiography conducted from a platform over a body of water.
(16) "Permanent radiographic installation" means ((a)) an
enclosed shielded ((installation or structure designed or
intended for radiography employing a radiographic exposure device
and)) room, cell or vault, not located at a temporary job site,
in which radiography is ((regularly)) performed, regardless of
ownership.
(((4) Personal supervision" means supervision by a
radiographer such that the radiographer is physically present at
the radiography site and in such proximity that communication can
be maintained and immediate assistance given as required. When a
radiographer's assistant is using or handling sources of
radiation, the radiographer must maintain direct surveillance.
(5))) (17) "Practical examination" means a demonstration through practical application of the safety rules and principles in industrial radiography including use of all appropriate equipment and procedures.
(18) "Radiation safety officer for industrial radiography" means an individual with the responsibility for the overall radiation safety program on behalf of the licensee and who meets the requirements of WAC 246-243-047.
(19) "Radiographer" means any individual who performs or who, in attendance at the site where sources of radiation are being used, personally supervises industrial radiographic operations and who is responsible to the licensee for assuring compliance with the requirements of these regulations and all license conditions.
(((6))) (20) "Radiographer certification" means written
approval received from a certifying entity stating that an
individual has satisfactorily met certain established radiation
safety, testing, and experience criteria.
(21) "Radiographer's assistant" means any individual who, under the personal supervision of a radiographer, uses sources of radiation, related handling tools, or radiation survey instruments in industrial radiography.
(((7))) (22) "Radiographic exposure device" means any
instrument containing a sealed source fastened or contained
therein, in which the sealed source or shielding thereof may be
moved, or otherwise changed, from a shielded to unshielded
position for purposes of making a radiographic exposure.
(((8))) (23) "Radiographic operations" means all activities
associated with the presence of radioactive sources in a
radiographic exposure device during use of the device or
transport (except when being transported by a common or contract
carrier), to include surveys to confirm the adequacy of
boundaries, setting up equipment and any activity inside
restricted area boundaries.
(24) "S-tube" means a tube through which the radioactive source travels when inside a radiographic exposure device.
(25) "Shielded position" means the location within the
radiographic exposure device or ((storage container which, by
manufacturer's design, is the proper location for storage of the
sealed source)) source changer where the sealed source is secured
and restricted from movement.
(((9))) (26) "Source assembly" means an assembly that
consists of the sealed source and a connector that attaches the
source to the control cable. The source assembly may also
include a stop ball used to secure the source in the shielded
position.
(27) "Source changer" means a device designed and used for replacement of sealed sources in radiographic exposure devices, including those also used for transporting and storage of sealed sources.
(((10))) (28) "Storage area" means any location, facility,
or vehicle which is used to store or to secure a radiographic
exposure device, a storage container, or a sealed source when it
is not in use and which is locked or has a physical barrier to
prevent accidental exposure, tampering with, or unauthorized
removal of the device, container, or source.
(29) "Storage container" means a ((device)) container in
which sealed sources are ((transported or)) secured and stored.
(((11))) (30) "Temporary job site" ((refers to any location
which is not specifically authorized and described in a license))
means a location where radiographic operations are conducted and
where licensed material may be stored other than those
location(s) of use authorized on the license.
(31) "Underwater radiography" means industrial radiography performed when the radiographic exposure device and/or related equipment are beneath the surface of the water.
[Statutory Authority: RCW 70.98.050. 94-01-073, § 246-243-020, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. 91-15-112 (Order 184), § 246-243-020, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. 91-02-049 (Order 121), recodified as § 246-243-020, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. 83-19-050 (Order 2026), § 402-36-025, filed 9/16/83. Statutory Authority: RCW 70.98.050. 81-01-011 (Order 1570), § 402-36-025, filed 12/8/80; Order 1084, § 402-36-025, filed 1/14/76.]
(1) Whenever radiography is performed at a location other than a permanent radiographic installation, the radiographer must be accompanied by at least one other qualified radiographer or an individual who has at a minimum met the requirements of WAC 246-243-130(2) (radiographer's assistant). The additional qualified individual shall observe the operations and be capable of providing immediate assistance to prevent unauthorized entry. Radiography may not be performed if only one qualified individual is present.
(2) All radiographic operations conducted at locations of use authorized on the license must be conducted in a permanent radiographic installation, unless specifically authorized by the department.
(3) Offshore platform, lay-barge, and/or underwater radiography shall be performed only by licensees whose license specifically authorizes such activity. Such operations fall under the jurisdiction of the United States Nuclear Regulatory Commission when conducted outside of the territorial waters of the state of Washington.
(4) Licensees will have until January 1, 2001, to meet the requirement for having two qualified individuals present at locations other than a permanent radiographic installation as specified in subsection (1) of this section.
[Statutory Authority: RCW 43.70.040. 91-02-049 (Order 121), recodified as § 246-243-030, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. 83-19-050 (Order 2026), § 402-36-027, filed 9/16/83.]
(1)
The licensee may not use a source changer or a container to store
licensed material unless the source changer or the storage
container has securely attached to it a durable, legible, and
clearly visible label bearing the standard trefoil radiation
caution symbol in conventional colors, i.e., magenta, purple or
black on a yellow background, having a minimum diameter of 25 mm,
and the wording:
RADIOACTIVE MATERIAL
NOTIFY CIVIL AUTHORITIES
(or "NAME OF COMPANY")
(2) The licensee may not transport licensed material unless the material is packaged, and the package is labeled, marked, and accompanied with appropriate shipping papers in accordance with regulations set out in 10 CFR Part 71.
(3) Locked radiographic exposure devices and storage containers must be physically secured to prevent tampering or removal by unauthorized personnel. The licensee shall store licensed material in a manner which will minimize danger from explosion or fire.
(4) The licensee shall lock and physically secure the transport package containing licensed material in the transporting vehicle to prevent accidental loss, tampering, or unauthorized removal of the licensed material from the vehicle.
[]
(1) Each licensee shall maintain records showing the receipts and transfers of sealed sources and of devices using depleted uranium (DU) for shielding and retain each record for three years after it is made.
(2) These records must include the date, shipper or destination, the name of the individual making the record, radionuclide, number of becquerels (curies) or mass (for DU), and manufacturer, model, and serial number of each sealed source and/or device, as appropriate.
[]
The radiation safety officer (RSO) shall ensure that radiation safety activities are being performed in accordance with approved procedures and regulatory requirements in the daily operation of the licensee's program.
(1) The minimum qualifications, training, and experience for RSOs for industrial radiography are as follows:
(a) Completion of the training and testing requirements of WAC 246-243-130(1);
(b) Two thousand hours of hands-on experience as a qualified radiographer in industrial radiographic operations utilizing sealed radioactive material; and
(c) Formal training in the establishment and maintenance of a radiation protection program.
(2) The department will consider alternatives when the RSO has appropriate training and/or experience in the field of ionizing radiation, and in addition, has adequate formal training with respect to the establishment and maintenance of a radiation safety protection program.
(3) The specific duties and authorities of the RSO include, but are not limited to:
(a) Establishing and overseeing all operating, emergency, and ALARA procedures as required by chapter 246-221 WAC, and reviewing them regularly to ensure that the procedures in use conform to current chapter 246-221 WAC requirements, conform to other department regulations and to the license conditions;
(b) Overseeing and approving all phases of the training program for radiographic personnel, ensuring that appropriate and effective radiation protection practices are taught;
(c) Ensuring that required radiation surveys and leak tests are performed and documented in accordance with the regulations, including any corrective measures when levels of radiation exceed established limits;
(d) Ensuring that personnel monitoring devices are calibrated and used properly by occupationally exposed personnel, that records are kept of the monitoring results, and that timely notifications are made as required by WAC 246-221-260; and
(e) Ensuring that operations are conducted safely and to assume control for instituting corrective actions including stopping of operations when necessary.
(4) The licensee will have until January 1, 2001, to meet the requirements of subsection (1) or (2) of this section.
[]
(1) Each licensee shall conduct the internal ((audit))
inspection of job performance required by WAC ((246-235-080
(5)(c))) 246-235-084 at intervals not to exceed ((three)) six
months. ((The audit should be done by management or the
radiation safety officer and shall cover a review or spot checks
of the records required by WAC 246-220-020, 246-221-110,
246-221-160, 246-221-230, 246-243-080, 246-243-090, 246-243-100,
246-243-110, 246-243-120, 246-243-130, 246-243-150, 246-243-190,
246-243-200, and 246-243-220, and conditions of the license.
(2) Each individual performing radiography shall be audited at intervals not to exceed three months during the performance of radiography, to assure that the license provisions, regulations, and the licensees operating and emergency procedures are followed by radiographers and radiographer's assistants. If a radiographer or a radiographer's assistant has not participated in a radiographic operation for more than three months since the last audit, that individual's performance must be observed and recorded the next time the individual participates in a radiographic operation. This audit shall be performed by the radiation safety officer, management, or the most experienced radiographers available. Results of this audit shall be recorded.
(3) Records of the internal audits required by subsections (1) and (2) of this section shall be maintained for three years.
(4) Training required by WAC 246-235-080 (5)(a) shall be conducted in accordance with the conditions of the license and subject to the following criteria:
(a) Initial training must be completed before a person can act as a radiographer or radiographer's assistant;
(b) Periodic retraining must be conducted at least annually;
(c) Records showing compliance with these training requirements must be maintained for at least one year following termination of employment.)) Except as provided in subsection (1)(d) of this section, the radiation safety officer (RSO) or designee shall conduct an inspection program of the job performance of each radiographer and radiographer's assistant to ensure that the department's regulations, license requirements, and the licensee's operating and emergency procedures are followed. The inspection program shall:
(a) Include observation of the performance of each radiographer and radiographer's assistant during an actual industrial radiographic operation, at intervals not to exceed six months; and
(b) Provide that, if a radiographer or a radiographer's assistant has not participated in an industrial radiographic operation for more than six months since the last inspection, the radiographer must demonstrate knowledge of the training requirements of WAC 246-243-130 (1)(c) and the radiographer's assistant must redemonstrate knowledge of the training requirements of WAC 246-243-130 (2)(b) by a practical examination before these individuals can next participate in a radiographic operation.
(c) The department may consider alternatives in situations where the individual serves as both radiographer and RSO.
(d) In operations where a single individual serves as both radiographer and RSO, and performs all radiography operations, an inspection program is not required.
(2) The licensee shall provide annual refresher safety training for each radiographer and radiographer's assistant at intervals not to exceed twelve months.
(3) Each licensee shall maintain the following records for three years after the record is made:
(a) For semi-annual inspection of job performance, the record shall include:
(i) A list of the items checked; and
(ii) Any noncompliances observed by the RSO;
(b) For annual refresher safety training, the record shall include:
(i) A list of the topics discussed;
(ii) The dates the training was conducted; and
(iii) Names of the instructors and attendees.
[Statutory Authority: RCW 70.98.050 and 70.98.080. 92-06-008 (Order 245), § 246-243-050, filed 2/21/92, effective 3/23/92. Statutory Authority: RCW 43.70.040. 91-02-049 (Order 121), recodified as § 246-243-050, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. 83-19-050 (Order 2026), § 402-36-035, filed 9/16/83.]
(1) Each radiographic exposure device shall be provided with a lock or outerlocked container designed to prevent unauthorized or accidental production of radiation or removal or exposure of a sealed source and shall be locked when returned to the shielded position at all times. If it is a keyed-lock, the key shall be removed at all times when not under the direct surveillance of a radiographer or a radiographer's assistant except at permanent radiographic installations as stated in WAC 246-243-170. In addition, during radiographic operations the sealed source assembly shall be locked in the shielded position each time the source is returned to that position.
(2) Each sealed source storage container and source changer shall have a lock or outer locked container designed to prevent unauthorized or accidental removal of the sealed source from its shielded position. Storage containers and source changers shall be kept locked (and if a keyed-lock, with the key removed at all times) when containing sealed sources except when under the direct surveillance of a radiographer or a radiographer's assistant.
(3) Radiographic exposure devices, source changers, and storage containers, prior to being moved from one location to another and also prior to being secured at a given location, shall be locked and surveyed to assure that the sealed source is in the shielded position.
[Statutory Authority: RCW 70.98.050 and 70.98.080. 91-15-112 (Order 184), § 246-243-060, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. 91-02-049 (Order 121), recodified as § 246-243-060, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.050. 81-01-011 (Order 1570), § 402-36-040, filed 12/8/80; Order 1084, § 402-36-040, filed 1/14/76; Order 1, § 402-36-040, filed 1/8/69; Rules (part), filed 10/26/66.]
(1) The
licensee shall maintain sufficient calibrated and operable
radiation survey instruments at each location where radioactive
material is present to make physical radiation surveys as
required by this part and chapter 246-221 WAC. Instrumentation
required by this section shall ((have a range such that two
milliroentgens per hour through one roentgen per hour can be
measured)) be capable of measuring a range from 0.02
millisieverts (2 millirems) per hour through 0.01 sievert (1 rem)
per hour.
(2) Each radiation survey instrument shall be calibrated:
(a) At ((energies appropriate for use and at)) intervals not
to exceed ((three)) six months and after each instrument
servicing except for battery changes;
(b) Such that accuracy within ± 20 percent ((traceable to a
national standard)) of the calibration source can be demonstrated
at each point checked; and
(c) ((At two or more widely separated points, other than
zero,)) For linear scale instruments, at two points located
approximately one-third and two-thirds of full scale on each
scale; for logarithmic scale instruments, at mid-range of each
decade; and for digital instruments at three points between 0.02
and 10 millisieverts (2 and 1000 millirems) per hour.
(3) Records shall be maintained of these calibrations for three years after the calibration date for inspection by the department.
[Statutory Authority: RCW 70.98.050. 94-01-073, § 246-243-080, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. 91-15-112 (Order 184), § 246-243-080, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. 91-02-049 (Order 121), recodified as § 246-243-080, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. 83-19-050 (Order 2026), § 402-36-060, filed 9/16/83. Statutory Authority: RCW 70.98.050. 81-01-011 (Order 1570), § 402-36-060, filed 12/8/80; Order 1084, § 402-36-060, filed 1/14/76; Order 1, § 402-36-060, filed 1/8/69; Rules (part), filed 10/26/66.]
(1) The replacement of any sealed source fastened to or contained in a radiographic exposure device and leak testing, repair, tagging, opening, or any other modification of any sealed source shall be performed only by persons specifically authorized to do so by the department, the United States Nuclear Regulatory Commission, or any agreement state.
(2) Each sealed source shall be tested for leakage at intervals not to exceed six months. Sealed sources that are in storage and not in use do not require leak testing, but must be tested before use or transfer to another person if the interval of storage exceeds six months. In the absence of a certificate from a transferor that a test has been made within the six-month period prior to the transfer, the sealed source shall not be put into use until tested and results obtained.
(3) The leak test shall be capable of detecting the presence of 185 becquerels (0.005 microcurie) of removable contamination on the sealed source. An acceptable leak test for sealed sources in the possession of a radiography licensee would be to test at the nearest accessible point to the sealed source storage position, or other appropriate measuring point where contamination might accumulate, by a procedure specifically approved in a license condition. Records of leak test results shall be kept in units of becquerels (microcuries) and maintained for inspection by the department for three years after the leak test is performed.
(4) Any test conducted ((pursuant to)) under subsections (2)
and (3) of this section which reveals the presence of 185
becquerels (0.005 microcurie) or more of removable radioactive
material shall be considered evidence that the sealed source is
leaking. The licensee shall immediately withdraw the equipment
involved from use and shall cause it to be decontaminated and
repaired or to be disposed in accordance with regulations of the
department. Within five days after obtaining results of the
test, the licensee shall file a report with the department
describing the involved equipment, the test results, and the
corrective action taken.
(5) Each exposure device using depleted uranium (DU) shielding and an "S" tube configuration must be tested for DU contamination at intervals not to exceed twelve months. The analysis must be capable of detecting the presence of 185 becquerels (0.005 microcuries) of radioactive material on the test sample and must be performed by a person specifically authorized by the department, the United States Nuclear Regulatory Commission or an agreement state to perform the analysis. If testing reveals the presence of 185 becquerels (0.005 microcuries) or more of removable DU contamination, the exposure device must be removed from use until an evaluation of the wear on the S-tube has been made. If the evaluation reveals that the S-tube is worn through, the device may not be used again. DU shielded devices do not have to be tested for DU contamination while in storage and not in use. Before using or transferring such a device however, the device must be tested for DU contamination if the interval of storage exceeded twelve months. A record of the DU leak-test results shall be kept in units of becquerels (microcuries) and maintained for inspection by the department for three years after the DU leak test is made or until the source in storage is removed. Licensees will have until January 1, 2001, to comply with the DU leak testing requirements of this section.
[Statutory Authority: RCW 70.98.050. 99-05-012, § 246-243-090, filed 2/5/99, effective 3/8/99; 94-01-073, § 246-243-090, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. 91-15-112 (Order 184), § 246-243-090, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. 91-02-049 (Order 121), recodified as § 246-243-090, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. 87-01-031 (Order 2450), § 402-36-070, filed 12/11/86; 83-19-050 (Order 2026), § 402-36-070, filed 9/16/83. Statutory Authority: RCW 70.98.050. 81-01-011 (Order 1570), § 402-36-070, filed 12/8/80; Order 1084, § 402-36-070, filed 1/14/76; Order 1, § 402-36-070, filed 1/8/69; Rules (part), filed 10/26/66.]
Each licensee shall conduct a quarterly physical inventory to account for all sealed sources and for devices containing depleted uranium (DU) received or possessed. The records of the inventories shall be maintained for three years from the date of inventory for inspection by the department and shall include:
(1) Exposure device or source changer make, model, and serial number;
(2) Sealed source serial number and manufacturer;
(3) Radionuclide and current activity in becquerels (curies) or mass (for DU) in each device;
(4) Location of sealed source and/or device/changer;
(5) Date of inventory;
(6) Name of person who performed inventory.
[Statutory Authority: RCW 70.98.050. 94-01-073, § 246-243-100, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 43.70.040. 91-02-049 (Order 121), recodified as § 246-243-100, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. 83-19-050 (Order 2026), § 402-36-080, filed 9/16/83. Statutory Authority: RCW 70.98.050. 81-01-011 (Order 1570), § 402-36-080, filed 12/8/80; Order 1084, § 402-36-080, filed 1/14/76; Order 1, § 402-36-080, filed 1/8/69; Rules (part), filed 10/26/66.]
(1) Each licensee shall maintain current logs, which shall be kept available for inspection by the department for three years from the date of the recorded event, at the address specified in the license showing for each sealed source and radiation exposure device the following information:
(a) A description (((or)) including the make ((and)), model
and serial number) of each radiation exposure device or transport
or storage container in which the sealed source is located:
(b) The identity and signature of the radiographer to whom assigned; and
(c) Locations where used and dates of use including the dates removed and returned to storage.
(2) A separately identified utilization log is not required if the equivalent information is available in records of the licensee and available at the address specified in the license.
[Statutory Authority: RCW 70.98.050. 94-01-073, § 246-243-110, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. 91-15-112 (Order 184), § 246-243-110, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. 91-02-049 (Order 121), recodified as § 246-243-110, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.050. 81-01-011 (Order 1570), § 402-36-090, filed 12/8/80; Order 1084, § 402-36-090, filed 1/14/76; Order 1, § 402-36-090, filed 1/8/69; Rules (part), filed 10/26/66.]
(1) ((The licensee shall conduct a program
for inspection and maintenance of radiographic exposure devices,
storage containers, control units (to include cables), and source
changers at intervals, not to exceed three months or prior to
first use thereafter to assure proper functioning of components
important to safety. Records of these inspections and
maintenance shall be kept for three years.
(2) The licensee shall check for obvious defects in radiographic exposure devices, storage containers, control assemblies, and source changers prior to use each day the equipment is used.
(3) The licensee's program shall include a thorough visual inspection for corrosion, and specific maintenance procedures that address corrosion removal and prevention.
(4) If any inspection conducted pursuant to subsections (1) or (2) of this section reveals damage to components critical to radiation safety, the device shall be removed from service until proper repairs have been made.
(5))) The licensee shall perform visual and operability checks on survey meters, radiographic exposure devices, transport and storage containers, associated equipment and source changers before use on each day the equipment is to be used to ensure that the equipment is in good working condition, that the sources are adequately shielded, and that required labeling is present. Survey instrument operability must be performed using check sources or other appropriate means. If equipment problems are found, the equipment must be removed from service until repaired.
(2) Each licensee shall have written procedures for:
(a) Inspection and routine maintenance of radiographic exposure devices, source changers, associated equipment, transport and storage containers, and survey instruments at intervals not to exceed three months or before the first use thereafter to ensure the proper functioning of components important to safety. Replacement components shall meet design specifications. If equipment problems are found, the equipment must be removed from service until repaired.
(b) Inspection and maintenance necessary to maintain the Type B packaging used to transport radioactive materials. The inspection and maintenance program must include procedures to assure that Type B packages are shipped and maintained in accordance with the certificate of compliance or other approval.
(3) Any maintenance performed on radiographic exposure devices and accessories shall be in accordance with the manufacturer's specifications.
(4) Records of daily checks and quarterly inspections including any equipment problems identified and of any maintenance performed under subsections (1) and (2) of this section shall be made and retained for three years. The record shall include:
(a) The date of check or inspection;
(b) Name of inspector;
(c) Equipment involved;
(d) Any problems found; and
(e) What repair and/or maintenance, if any, was done.
[Statutory Authority: RCW 70.98.050. 94-01-073, § 246-243-120, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. 91-15-112 (Order 184), § 246-243-120, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. 91-02-049 (Order 121), recodified as § 246-243-120, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. 83-19-050 (Order 2026), § 402-36-095, filed 9/16/83. Statutory Authority: RCW 70.98.050. 81-01-011 (Order 1570), § 402-36-095, filed 12/8/80; Order 1084, § 402-36-095, filed 1/14/76.]
(1) No licensee shall permit any individual to act as a radiographer as defined in this chapter until such individual:
(a) Has been instructed in the subjects outlined in WAC 246-243-230, in addition to a minimum of two months of on-the-job training, and is certified through a radiographer certification program by a certifying entity in accordance with the criteria specified in WAC 246-243-250, Appendix C or equivalent regulations of the United States Nuclear Regulatory Commission or an agreement state. The department maintains a list of recognized certifying entities for reference. The licensee may, until January 1, 2001, allow an individual who has not met the requirement of this subsection, to act as a radiographer after the individual has received training in the subjects outlined in WAC 246-243-230 and demonstrated an understanding of these subjects by successful completion of a written examination that was previously submitted to and approved by the department;
(b) Has received copies of and instruction in the
regulations contained in chapters 246-220, ((246-222,)) 246-221,
246-222, 246-231, and 246-243 WAC, in the United States
Department of Transportation regulations as referenced in chapter 246-231 WAC, and the applicable sections of appropriate
license(s), and the licensee's operating and emergency
procedures, and shall have demonstrated understanding thereof by
successful completion of a written or oral examination covering
this material;
(c) Has ((demonstrated competence to use the source of
radiation, related handling tools, and radiation survey
instruments which will be employed in the individual's
assignment)) received training in the use of the licensee's
radiographic exposure devices, sealed sources, in the daily
inspection of devices and associated equipment, and in the use of
radiation survey instruments; and
(d) Has demonstrated understanding of the ((instructions in
this paragraph)) use of radiographic exposure devices, sources,
survey instruments and associated equipment described in
subsection (1)(c) of this section by successful completion of
((written test and a field)) a practical examination on the
subjects covered.
(2) No licensee shall permit any individual to act as a
radiographer's assistant as defined in this ((part)) chapter
until such individual:
(a) Has received copies of and instruction in the regulations contained in chapters 246-220, 246-221, 246-222, 246-231,and 246-243 WAC, in the United States Department of Transportation regulations as referenced in chapter 246-231 WAC, and the applicable sections of appropriate license(s), and the licensee's operating and emergency procedures;
(b) Has ((demonstrated)) developed competence to use under
the personal supervision of the radiographer the ((sources of
radiation, related handling tools)) radiographic exposure
devices, sealed sources, associated equipment, and radiation
survey instruments which will be employed in the individual's
assignment; and
(c) Has demonstrated understanding of the instructions ((in
this paragraph)) provided under (a) of this subsection by
successfully completing a written ((or oral)) test ((and a
field)) on the subjects covered and has demonstrated competence
in the use of the hardware described in (b) of this subsection by
successful completion of a practical examination on the
((subjects covered; and
(d) Records of the above training including copies of written tests and dates of oral tests and field examinations shall be maintained for at least one year following termination of employment)) use of such hardware.
(3) Each licensee shall maintain, for inspection by the
department, records of training and ((testing)) certification
which demonstrate that the requirements of subsections (1) and
(2) of this section ((and WAC 246-235-080 (5)(a))) are met.
These records shall be maintained for three years after the
record is made. The record shall include:
(a) Radiographer certification documents and verification of certification status;
(b) Copies of written tests;
(c) Dates of oral and practical examinations; and
(d) Names of individuals conducting and receiving the oral and practical examinations.
(4) Licensees will have until January 1, 2001, to comply with the certification requirements specified in subsection (1)(a) of this section, and the additional training requirements specified in subsections (1)(b) and (2)(a) of this section.
[Statutory Authority: RCW 70.98.050. 94-01-073, § 246-243-130, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. 91-15-112 (Order 184), § 246-243-130, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. 91-02-049 (Order 121), recodified as § 246-243-130, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. 83-19-050 (Order 2026), § 402-36-100, filed 9/16/83. Statutory Authority: RCW 70.98.050. 81-01-011 (Order 1570), § 402-36-100, filed 12/8/80; Order 1084, § 402-36-100, filed 1/14/76; Order 1, § 402-36-100, filed 1/8/69; Rules (part), filed 10/26/66.]
The licensee's operating and emergency procedures shall include instructions in at least the following:
(1) The handling and use of sources of radiation to be employed such that no individual is likely to be exposed to radiation doses in excess of the limits established in chapter 246-221 WAC Standards for protection against radiation;
(2) Methods and occasions for conducting radiation surveys;
(3) Methods for controlling access to radiographic areas;
(4) Methods and occasions for locking and securing sources of radiation including radiographic exposure devices, transport and storage containers, and sealed sources;
(5) Personnel monitoring and the use of personnel monitoring
equipment including steps that must be taken immediately by
radiography personnel ((in the event)) if a pocket dosimeter is
found to be off-scale or an alarm rate meter alarms unexpectedly;
(6) Transportation to field locations, including packing of
sources of radiation in the vehicles, ((posting)) placarding of
vehicles when needed, and control of sources of radiation during
transportation;
(7) Minimizing exposure of individuals in the event of an accident;
(8) Notifying proper personnel in the event of a theft, loss, overexposure or accident involving sources of radiation;
(9) Maintenance of records;
(10) The inspection ((and)), maintenance, and operability
checks of radiographic exposure devices, survey instruments,
transport containers, and storage containers; ((and))
(11) Identifying and reporting defects and noncompliance as required by these regulations; and
(12) Source recovery procedures if the licensee will perform source recovery.
[Statutory Authority: RCW 70.98.050. 94-01-073, § 246-243-140, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. 91-15-112 (Order 184), § 246-243-140, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. 91-02-049 (Order 121), recodified as § 246-243-140, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. 83-19-050 (Order 2026), § 402-36-110, filed 9/16/83. Statutory Authority: RCW 70.98.050. 81-01-011 (Order 1570), § 402-36-110, filed 12/8/80; Order 1084, § 402-36-110, filed 1/14/76; Order 708, § 402-36-110, filed 8/24/72; Order 1, § 402-36-110, filed 7/2/71; Order 1, § 402-36-110, filed 1/8/69; Rules (part), filed 10/26/66.]
Each licensee shall maintain a copy of current operating and emergency procedures until the department terminates the license. Superceded material shall be retained for three years after the change is approved.
[]
(1) No licensee shall permit any individual to act as a radiographer or as a radiographer's assistant unless, at all times during radiographic operations, each such individual shall wear on the trunk of the body a combination of an approved personnel dosimeter such as a film or TLD badge, a direct reading pocket dosimeter, and an alarming rate meter. In permanent facilities where other appropriate alarming or warning devices are in routine use, the wearing of an alarming rate meter is not required.
(a) Pocket dosimeters shall be capable of measuring exposures from zero to at least 200 milliroentgens. Electronic personal dosimeters may only be used in place of ion-chamber pocket dosimeters.
(b) A film or TLD badge or other approved personnel dosimeter shall be assigned to and worn by only one individual.
(c) Film badges must be replaced at periods not to exceed one month and TLDs must be replaced at periods not to exceed three months.
(d) After replacement, each film badge or TLD must be processed as soon as possible.
(2)(a) Direct reading dosimeters such as pocket dosimeters
or electronic personal dosimeters shall be read and exposures
recorded ((daily)) at the beginning and end of each shift. Pocket dosimeters shall be charged at the beginning of each
((working day)) shift. Pocket dosimeters shall be checked
annually at periods not to exceed ((thirteen)) twelve months for
correct response to radiation. Acceptable dosimeters shall read
within plus or minus twenty percent of the true radiation
exposure.
(b) Each alarming rate meter must:
(i) Be checked to ensure that the alarm functions properly (sounds) prior to use at the start of each shift;
(ii) Be set to give an alarm signal at a maximum preset rate of 5 mSv/hr. (500 mR/hr.);
(iii) Require special means to change the preset alarm functions; and
(iv) Be calibrated annually at periods not to exceed
((thirteen)) twelve months for correct response to radiation:
Acceptable rate meters must alarm within plus or minus twenty
percent of the true radiation exposure rate.
(((c) A film or TLD badge shall be immediately processed if
a pocket dosimeter is discharged beyond its range during normal
use. The film or TLD badge reports received from the film or TLD
badge processor and records of pocket dosimeter readings shall be
maintained for inspection by the department until it authorizes
their disposal.)) (3) If an individual's pocket dosimeter is
found to be off-scale, or if his or her electronic personal
dosimeter reads greater than 2 millisieverts (200 millirems), and
the possibility of radiation exposure cannot be ruled out as the
cause, the individual's film badge or TLD must be sent for
processing within twenty-four hours. In addition, the individual
may not resume work associated with licensed material use until a
determination of the individual's radiation exposure has been
made. This determination shall be made by the RSO or the RSO's
designee.
(4) If a film badge or TLD is lost or damaged, the worker shall cease work immediately until a replacement film badge or TLD is provided and the exposure is calculated for the time period from issuance to loss or damage of the film badge or TLD.
(5) Each licensee shall maintain the following exposure records:
(a) Direct reading dosimeter readings and yearly operability checks required by subsection (2) of this section for three years after the record is made.
(b) Records of alarm rate meter calibrations for three years after the record is made.
(c) Reports received from the film badge or TLD processor until the department terminates the licensee.
(d) Records of estimates of exposures as a result of: Off-scale personal direct reading dosimeters, or lost or damaged film badges or TLDs, until the department terminates the license.
[Statutory Authority: RCW 70.98.050. 94-01-073, § 246-243-150, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. 91-15-112 (Order 184), § 246-243-150, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. 91-02-049 (Order 121), recodified as § 246-243-150, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. 83-19-050 (Order 2026), § 402-36-120, filed 9/16/83. Statutory Authority: RCW 70.98.050. 81-01-011 (Order 1570), § 402-36-120, filed 12/8/80; Order 1084, § 402-36-120, filed 1/14/76; Order 1, § 402-36-120, filed 1/8/69; Rules (part), filed 10/26/66.]
Whenever a radiographer's assistant uses radiographic exposure
devices, uses sealed sources or ((related source handling tools))
associated equipment, or conducts radiation surveys required by
WAC 246-243-190 (((2), (3), (4), or (5))) to determine that the
sealed source has returned to the shielded position after an
exposure, he or she shall be under the personal supervision of a
radiographer, as defined in WAC 246-243-020. Personal
supervision shall include (1) the radiographer's personal
presence at the site where the sealed sources are being used, (2)
the ability of the radiographer to communicate and give immediate
assistance if required, and (3) the radiographer's ability to
observe the performance of his/her assistant during the
operations referred to in this section.
[Statutory Authority: RCW 70.98.050. 94-01-073, § 246-243-160, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. 91-15-112 (Order 184), § 246-243-160, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. 91-02-049 (Order 121), recodified as § 246-243-160, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. 83-19-050 (Order 2026), § 402-36-125, filed 9/16/83. Statutory Authority: RCW 70.98.050. 81-01-011 (Order 1570), § 402-36-125, filed 12/8/80.]
(1) During each radiographic operation,
the radiographer or radiographer's assistant shall maintain ((a))
continuous direct visual surveillance of the operation to protect
against unauthorized entry into a high radiation area, as defined
in chapter 246-220 WAC except:
(((a) Where the high radiation area is equipped with a
control device or alarm system as described in WAC 246-221-102(1); or
(b) Where the high radiation area is locked to protect against unauthorized or accidental entry.)) At permanent radiographic installations where all entryways are locked and the requirements of WAC 246-243-220 are met.
(2) When not in operation or when not under direct surveillance, portable radiation exposure devices shall be physically secured to prevent removal by unauthorized personnel.
[Statutory Authority: RCW 70.98.050. 94-01-073, § 246-243-170, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. 91-15-112 (Order 184), § 246-243-170, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. 91-02-049 (Order 121), recodified as § 246-243-170, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.050. 81-01-011 (Order 1570), § 402-36-130, filed 12/8/80; Order 1084, § 402-36-130, filed 1/14/76; Order 1, § 402-36-130, filed 1/8/69; Rules (part), filed 10/26/66.]
((Notwithstanding any provisions
in paragraph WAC 246-221-130 areas in which radiography is being
performed or in which a radiographic exposure device is being
stored shall be conspicuously posted and access to the area shall
be controlled as required by WAC 246-221-120 and 246-221-102(1).
(1) All potential radiation areas where industrial radiographic operations are to be performed shall be posted based on calculated or estimated exposure rates before industrial radiography operations begin.
(2) Each time the exposure device is relocated and/or the exposed position of the sealed source is changed, the requirements of subsection (1) of this section shall be met.)) All areas in which industrial radiography is being performed shall be conspicuously posted as required by WAC 246-221-120. Exceptions listed in WAC 246-221-130 do not apply to industrial radiographic operations.
[Statutory Authority: RCW 70.98.050. 94-01-073, § 246-243-180, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. 91-15-112 (Order 184), § 246-243-180, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. 91-02-049 (Order 121), recodified as § 246-243-180, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.050. 81-01-011 (Order 1570), § 402-36-140, filed 12/8/80; Order 1084, § 402-36-140, filed 1/14/76; Order 1, § 402-36-140, filed 1/8/69; Rules (part), filed 10/26/66.]
(((1) No radiographic operation shall be conducted unless
calibrated and operable radiation survey instrumentation as
described in WAC 246-243-080 is available and used at each site
where radiographic operations are being performed and at the
storage area whenever a radiographic exposure device, a storage
container, or source is being placed in storage.
(2) A physical radiation survey shall be made after each radiographic exposure utilizing radiographic exposure devices or sealed sources of radioactive material to determine that the sealed source has been returned to its shielded position. The horizontal circumference of the radiographic exposure device shall be surveyed. If the radiographic exposure device has a source guide tube, the survey shall include the guide tube.
(3) A physical radiation survey shall be made to determine that each sealed source is in its shielded condition prior to securing the radiographic exposure device or storage container as specified in WAC 246-243-060. The horizontal circumference of the radiographic exposure device shall be surveyed. If the radiographic exposure device has a source guide tube, the survey shall include the guide tube.
(4))) The licensee shall:
(1) Conduct surveys with a calibrated and operable radiation survey instrument that meets the requirements of WAC 246-243-080.
(2) Using a survey instrument meeting the requirements of subsection (1) of this section, conduct a survey of the radiographic exposure device and the guide tube after each exposure when approaching the device or the guide tube. The survey shall determine that the sealed source has returned to its shielded position before exchanging films, repositioning the exposure head, or dismantling equipment.
(3) Conduct a survey of the radiographic exposure device with a calibrated radiation survey instrument any time the source is exchanged and whenever a radiographic exposure device is placed in a storage area to ensure that the sealed source is in its shielded position.
(4) Conduct a physical radiation survey ((shall be made)) of
the boundary of the restricted area during radiographic
operations not employing shielded room radiography. The maximum
survey reading at the boundary shall be recorded. The records
shall indicate approximate distance from source to boundaries,
whether or not the exposed source is collimated and any occupied
areas with exposure levels greater than 2 mR in any hour during
radiographic operations.
(5) ((A survey with a calibrated and operable survey
instrument shall be made any time a radiographic exposure device
is placed into the storage area to ensure that the sealed source
is in its shielded position. The horizontal circumference of the
radiographic exposure device with emphasis on the source exit
port must be surveyed.
(6))) Maintain a record of each exposure device survey
conducted before the device is placed in storage if that survey
is the last one performed in the workday, and records required by
subsection((s (3),)) (4)((, and (5))) of this section ((shall
include)), including the model and serial number of the survey
meter used ((and shall be maintained)), for inspection by the
department for three years after completion of the survey. If
the survey was used to determine an individual's exposure,
however, the records of the survey shall be maintained until the
department authorizes their disposition.
[Statutory Authority: RCW 70.98.050. 94-01-073, § 246-243-190, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. 92-06-008 (Order 245), § 246-243-190, filed 2/21/92, effective 3/23/92. Statutory Authority: RCW 43.70.040. 91-02-049 (Order 121), recodified as § 246-243-190, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. 83-19-050 (Order 2026), § 402-36-150, filed 9/16/83. Statutory Authority: RCW 70.98.050. 81-01-011 (Order 1570), § 402-36-150, filed 12/8/80; Order 1084, § 402-36-150, filed 1/14/76; Order 1, § 402-36-150, filed 1/8/69; Rules (part), filed 10/26/66.]
(1) In addition to the reporting requirements specified in other sections of the regulations, each licensee shall provide a written report to the department within thirty days of the occurrence of any of the following incidents involving radiographic equipment:
(a) Unintentional disconnection of the source assembly from the control cable.
(b) Inability to retract the source assembly to its fully shielded position and secure it in this position.
(c) Failure of any component (critical to safe operation of the device) to properly perform its intended function.
(2) The licensee shall include the following information in each report submitted under subsection (1) of the section.
(a) A description of the equipment problem;
(b) Cause of each incident, if known;
(c) Manufacturer and model number of equipment involved in the incident;
(d) Place, time, and date of incident;
(e) Actions taken to reestablish normal operations;
(f) Corrective actions taken or planned to prevent recurrence;
(g) Qualifications of personnel involved in the incident.
(3) Reports of overexposure submitted under WAC 246-221-260 which involve failure of safety components of radiographic equipment must also include the information specified in subsection (2) of this section.
(4) Any licensee conducting radiographic operations or storing radioactive material at any location not listed on the license for a period in excess of one hundred eighty days in a calendar year, shall notify the department prior to exceeding the one hundred eighty days.
[Statutory Authority: RCW 70.98.050. 94-01-073, § 246-243-195, filed 12/9/93, effective 1/9/94.]
Each licensee conducting radiographic operations at a temporary site shall have copies of the following documents and records available at that site for inspection by the department:
(1) Appropriate license;
(2) Operating and emergency procedures;
(3) Applicable regulations;
(4) Survey records required pursuant to WAC 246-243-190 for the period of operation at the site;
(5) ((Daily pocket)) Direct reading dosimeter records for
the period of operation at the site;
(6) The latest radiation survey instrument calibration record and leak test record for specific devices in use at the site;
(7) The latest calibration record for alarm rate meters and operability checks of pocket dosimeters and/or electronic personal dosimeters as required by WAC 246-243-150;
(8) Utilization records for each radiographic exposure device dispatched from that location as required by WAC 246-243-110;
(9) Records of equipment problems identified in daily checks of equipment as required by WAC 246-243-120;
(10) Records of alarm system and entrance control checks required by WAC 246-243-220, if applicable;
(11) The shipping papers for the transportation of radioactive materials; and
(12) When operating under reciprocity pursuant to WAC 246-232-040, a copy of the NRC or agreement state license authorizing the use of radioactive material.
[Statutory Authority: RCW 70.98.050. 94-01-073, § 246-243-200, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. 91-15-112 (Order 184), § 246-243-200, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. 91-02-049 (Order 121), recodified as § 246-243-200, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.050. 81-01-011 (Order 1570), § 402-36-153, filed 12/8/80.]
Each record required by this chapter must be legible throughout the specified retention period. The record may be the original or a reproduced copy or a microform provided that the copy or microform is authenticated by authorized personnel and that the microform is capable of reproducing a clear copy throughout the required retention period. The record may also be stored in electronic media with the capability for producing legible, accurate, and complete records during the required retention period. Records, such as letters, drawings, and specifications, must include all pertinent information, such as stamps, initials, and signatures. The licensee shall maintain adequate safeguards against tampering with and loss of records.
[]
((Permanent radiographic
installations having high radiation area entrance controls of the
types described in WAC 246-221-102(1) or where the high radiation
area is locked to protect against unauthorized or accidental
entry, shall also meet the following special requirements.))
(1) Each entrance that is used for personnel access to the high radiation area in a permanent radiographic installation to which this section applies shall have either:
(a) An entrance control of the type described in WAC 246-221-102(1) that reduces the radiation level upon entry into the area; or
(b) Both conspicuous visible and audible warning signals to warn of the presence of radiation. The visible signal shall be actuated by radiation whenever the source is exposed. The audible signal shall be actuated when an attempt is made to enter the installation while the source is exposed.
(2) ((Both visible and audible alarm systems are required
and shall be tested prior to the first use of a source in the
installation and thereafter at intervals not to exceed three
months. Records of the tests shall be kept)) The alarm system
must be tested for proper operation with a radiation source each
day before the installation is used for radiographic operations.
The test must include a check of both the visible and audible
signals. Entrance control devices that reduce the radiation
level upon entry (designated in subsection (1)(a) of this
section) shall be tested monthly. If an entrance control device
or an alarm is operating improperly, it must be immediately
labeled as defective and repaired within seven calendar days.
The facility may continue to be used during this seven-day
period, provided the licensee implements the continuous
surveillance requirements of WAC 246-243-170 and uses an alarming
rate meter. Test records for entrance controls and audible and
visual alarm must be maintained for three years after the record
is made.
(3) The department shall review and approve, in advance of construction, plans for permanent radiographic installations whose construction had not commenced by the effective date of these regulations. Construction of the permanent facility shall be in accordance with the plans approved by the department.
(4) A physical radiation survey shall be conducted and results recorded following construction or major modification of the facility to be used in the installation. Radiography shall not be conducted if exposure levels in unrestricted areas are greater than 2 mR in any hour. Any increase in source strength will require resurvey of the installation prior to the conduct of industrial radiography.
[Statutory Authority: RCW 70.98.050. 94-01-073, § 246-243-220, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050 and 70.98.080. 91-15-112 (Order 184), § 246-243-220, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. 91-02-049 (Order 121), recodified as § 246-243-220, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. 83-19-050 (Order 2026), § 402-36-157, filed 9/16/83. Statutory Authority: RCW 70.98.050. 81-01-011 (Order 1570), § 402-36-157, filed 12/8/80.]
(1) Fundamentals of radiation safety
(a) Characteristics of ionizing radiation
(b) Units of radiation dose (((mrem))) and quantity of
radioactivity (((curie)))
(c) Hazards of exposure to radiation
(i) Radiation protection standards
(ii) Biological effects of radiation dose
(d) Levels of radiation from sources of radiation
(e) Methods of controlling radiation dose
(i) Working time
(ii) Working distances
(iii) Shielding
(2) Radiation detection instrumentation to be used
(a) Use of radiation survey instruments
(i) Operation
(ii) Calibration
(iii) Limitations
(b) Survey techniques
(c) Use of personnel monitoring equipment
(i) Film badges
(ii) Pocket dosimeters
(iii) Thermoluminescent dosimeters
(iv) Alarming rate meters
(3) Radiographic equipment to be used
(a) Operation and control of remote handling equipment, radiographic exposure equipment, and storage containers, including pictures or models of source assemblies (pigtails)
(b) ((Radiographic exposure devices and sealed sources))
Inspection and maintenance of equipment
(c) Storage ((containers)), control, and disposal of
licensed material
(4) The requirements of pertinent federal and state regulations
(5) The licensee's written operating and emergency procedures
(6) Case histories of radiography accidents.
[Statutory Authority: RCW 70.98.050. 94-01-073, § 246-243-230, filed 12/9/93, effective 1/9/94. Statutory Authority: RCW 43.70.040. 91-02-049 (Order 121), recodified as § 246-243-230, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.050. 81-01-011 (Order 1570), § 402-36-160, filed 12/8/80; Order 1084, § 402-36-160, filed 1/14/76; Order 1, § 402-36-160, filed 1/8/69; Rules (part), filed 10/26/66.]
(1) Requirements for an independent certifying organization. An independent certifying organization shall:
(a) Be an organization such as a society or association, whose members participate in, or have an interest in, the fields of industrial radiography;
(b) Make its membership available to the general public nationwide that is not restricted because of race, color, religion, sex, age, national origin or disability;
(c) Have a certification program open to nonmembers, as well as members;
(d) Be an incorporated, nationally recognized organization that is involved in setting national standards of practice within its fields of expertise;
(e) Have an adequate staff, a viable system for financing its operations, and a policy- and decision-making review board;
(f) Have a set of written organizational by-laws and policies that provide adequate assurance of lack of conflict of interest and a system for monitoring and enforcing those by-laws and policies;
(g) Have a committee, whose members can carry out their responsibilities impartially, to review and approve the certification guidelines and procedures, and to advise the organization's staff in implementing the certification program.
(h) Have a committee, whose members can carry out their responsibilities impartially, to review complaints against certified individuals and to determine appropriate sanctions;
(i) Have written procedures describing all aspects of its certification program, maintain records of the current status of each individual's certification and the administration of its certification program;
(j) Have procedures to ensure that certified individuals are provided due process with respect to the administration of its certification program, including the process of becoming certified and any sanctions imposed against certified individuals;
(k) Have procedures for proctoring examinations, including qualifications for proctors. These procedures must ensure that the individuals proctoring each examination are not employed by the same company or corporation (or a wholly owned subsidiary of such company or corporation) as any of the examinees;
(l) Exchange information about certified individuals with the department, the US Nuclear Regulatory Commission, other independent certifying organizations and/or agreement states and allow periodic review of its certification program and related records; and
(m) Provide a description to the department of its procedures for choosing examination sites and for providing an appropriate examination environment.
(2) Requirements for certification programs. All certification programs must:
(a) Require applicants for certification to:
(i) Receive training in the topics set forth in WAC 246-243-230 or equivalent NRC or agreement state regulations; and
(ii) Satisfactorily complete a written examination covering these topics;
(b) Require applicants for certification to provide documentation that demonstrates that the applicant has:
(i) Received training in the topics set forth in WAC 246-243-230 or equivalent NRC or agreement state regulations;
(ii) Satisfactorily completed a minimum period of on-the-job training; and
(iii) Received verification by an agreement state or a NRC licensee that the applicant has demonstrated the capability of independently working as a radiographer;
(c) Include procedures to ensure that all examination questions are protected from disclosure;
(d) Include procedures for denying an application, revoking, suspending, and reinstating a certificate;
(e) Provide a certification period of not less than three years nor more than five years;
(f) Include procedures for renewing certifications and, if the procedures allow renewals without examination, require evidence of recent full-time employment and annual refresher training;
(g) Provide a timely response to inquiries, by telephone or letter, from members of the public, about an individual's certification status.
(3) Requirements for written examinations.
All examinations must be:
(a) Designed to test an individual's knowledge and understanding of the topics listed in WAC 246-243-230 or equivalent NRC or agreement state requirements;
(b) Written in a multiple-choice format;
(c) Have test items drawn from a question bank containing psychometrically valid questions based on the material in WAC 246-243-230.
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The following section of the Washington Administrative Code is repealed:
| WAC 246-243-210 | Special requirements for enclosed radiography. |