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Chapter 246-232 WAC

Last Update: 12/12/16

RADIOACTIVE MATERIAL—LICENSING APPLICABILITY

WAC Sections

HTMLPDF246-232-001Purpose and scope.
HTMLPDF246-232-006Exemption of certain source material.
HTMLPDF246-232-007Exemption of certain depleted uranium items.
HTMLPDF246-232-008Exemption of certain timepieces, hands or dials.
HTMLPDF246-232-009Exemption of certain items containing radioactive material.
HTMLPDF246-232-010Exempt concentrations and exempt quantities.
HTMLPDF246-232-011Exemption of certain self-luminous products containing radioactive material(s).
HTMLPDF246-232-012Exemption of certain gas and aerosol detectors containing radioactive material.
HTMLPDF246-232-014Exemption of C-14 urea diagnostic capsules for human use.
HTMLPDF246-232-015Certain industrial devices.
HTMLPDF246-232-020Types of licenses.
HTMLPDF246-232-030Prelicensing inspection.
HTMLPDF246-232-040Reciprocal recognition of licenses.
HTMLPDF246-232-050Terms and conditions of licenses.
HTMLPDF246-232-060Termination of licenses and decommissioning of sites and separate buildings or outdoor areas.
HTMLPDF246-232-070Modification and revocation of licenses.
HTMLPDF246-232-080Transfer of material.
HTMLPDF246-232-090Transportation.
HTMLPDF246-232-120Schedule B, exempt quantities of radioactive materials.
HTMLPDF246-232-130Schedule C, exempt concentrations.
HTMLPDF246-232-140Schedule D.
HTMLPDF246-232-990Fees.
DISPOSITION OF SECTIONS FORMERLY CODIFIED IN THIS TITLE
246-232-013Exemption of certain resins containing scandium-46 and designed for sand consolidation in oil wells. [Statutory Authority: RCW 70.98.050. WSR 01-02-068, § 246-232-013, filed 12/29/00, effective 1/29/01.] Repealed by WSR 13-24-025, filed 11/22/13, effective 12/23/13. Statutory Authority: RCW 70.98.050.
246-232-100Requirements for users of the Washington commercial low-level waste disposal site. [Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-232-100, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080 and chapter 70.121 RCW. WSR 86-17-027 (Order 2406), § 402-19-530, filed 8/13/86. Statutory Authority: RCW 70.98.080. WSR 83-19-050 (Order 2026), § 402-19-530, filed 9/16/83. Statutory Authority: RCW 70.98.050. WSR 81-01-011 (Order 1570), § 402-19-530, filed 12/8/80. Statutory Authority: RCW 70.98.080. WSR 80-02-080 (Order 1481), § 402-19-530, filed 1/21/80.] Repealed by WSR 91-15-112 (Order 184), filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 70.98.050 and 70.98.080.
246-232-110Large volumes of naturally occurring material. [Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-232-110, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080 and chapter 70.121 RCW. WSR 86-17-027 (Order 2406), § 402-19-540, filed 8/13/86.] Repealed by WSR 91-15-112 (Order 184), filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 70.98.050 and 70.98.080.


PDF246-232-001

Purpose and scope.

(1) This chapter prescribes rules governing licensing of radioactive material. No person shall manufacture, produce, transfer, receive, acquire, own, possess, or use radioactive material except:
(a) As authorized in a specific or general license issued under chapters 246-233 or 246-235 WAC;
(b) As authorized in a specific or general license issued under regulations of NRC or an agreement state equivalent to chapters 246-233 or 246-235 WAC; or
(c) As otherwise provided in this chapter.
(2) In addition to the requirements of this chapter, and chapters 246-233 or 246-235 WAC, all licensees must comply with chapters 246-220, 246-221, 246-222, 246-231, 246-247, and 246-254 WAC. Licensees engaged in the practice of nuclear medicine are subject to chapter 246-240 WAC, licensees engaged in industrial radiographic operations are subject to chapter 246-243 WAC, licensees using sealed sources in the healing arts are subject to chapter 246-240 WAC, licensees using radioactive material in well logging and subsurface tracer studies are subject to chapter 246-244 WAC, licensees engaged in land disposal of radioactive waste are subject to chapter 246-250 WAC, and licensees owning or operating uranium or thorium mills and associated mill tailings are subject to chapter 246-252 WAC.
(3) No person may introduce radioactive material into a product or material, knowing or having reason to believe that it will be transferred to persons exempt under this section or other sections or equivalent regulations of the NRC or an agreement state, except in accordance with a specific license issued by the NRC, Washington, D.C. 20555.
[Statutory Authority: RCW 70.98.050. WSR 13-24-025, § 246-232-001, filed 11/22/13, effective 12/23/13; WSR 06-05-019, § 246-232-001, filed 2/6/06, effective 3/9/06; WSR 99-15-105, § 246-232-001, filed 7/21/99, effective 8/21/99. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 91-15-112 (Order 184), § 246-232-001, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-232-001, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. WSR 83-19-050 (Order 2026), § 402-19-010, filed 9/16/83; WSR 79-12-073 (Order 1459), § 402-19-010, filed 11/30/79, effective 1/1/80. Formerly chapter 402-20 WAC.]



PDF246-232-006

Exemption of certain source material.

(1) A person is exempt from the requirements for a license and from this chapter and chapters 246-233 and 246-235 WAC to the extent that the person receives, possesses, uses, transfers, or delivers, source material in any chemical mixture, compound, solution or alloy in which the source material is by weight less than 1/20 of one percent (0.05 percent) of the mixture, compound, solution, or alloy.
(2) A person is exempt from the requirements for a license and from this chapter and chapters 246-233 and 246-235 WAC to the extent that the person receives, possesses, uses or transfers unrefined and unprocessed ore containing source material, provided such person shall not refine or process such ore unless authorized to do so in a specific license.
(3) A person is exempt from the requirements for a license and from this chapter and chapters 246-221, 246-246, 246-222, 246-233, and 246-235 WAC to the extent that the person receives, possesses, uses or transfers:
(a) Any quantities of thorium contained in:
(i) Incandescent gas mantles;
(ii) Vacuum tubes;
(iii) Welding rods;
(iv) Electric lamps for illuminating purposes if each lamp contains fifty milligrams or less of thorium;
(v) Germicidal lamps, sunlamps and lamps for outdoor or industrial lighting if each lamp contains two grams or less of thorium;
(vi) Rare earth metals and compounds, mixtures, and products containing 0.25 percent or less by weight thorium, uranium, or any combination of these; or
(vii) Personnel neutron dosimeters if each dosimeter contains 1.85 gigabecquerels (50 milligrams) or less of thorium.
(b) Source material contained in the following products:
(i) Glazed ceramic tableware manufactured before August 27, 2013, if the glaze contains twenty percent or less by weight source material;
(ii) Piezoelectric ceramic containing two percent or less by weight source material; and
(iii) Glassware containing not more than two percent by weight source material or, for glassware manufactured before August 27, 2013, ten percent by weight source material; but not including commercially manufactured glass brick, pane glass, ceramic tile, or other glass or ceramic used in construction.
(c) Photographic film, negatives and prints containing uranium or thorium;
(d) Any finished product or part fabricated of, or containing, tungsten-thorium or magnesium-thorium alloys if the thorium content of the alloy is four percent or less by weight. The exemption contained in this subparagraph shall not be deemed to authorize the chemical, physical or metallurgical treatment or processing of any such product or part;
(e) Thorium or uranium contained in or on finished optical lenses and mirrors, provided that each lens or mirror does not contain more than ten percent by weight of thorium or uranium or, for lenses manufactured before August 27, 2013, thirty percent by weight of thorium. The exemption contained in this subparagraph shall not be deemed to authorize either:
(i) The shaping, grinding or polishing of such lens or mirror or manufacturing processes other than the assembly of such lens or mirror into optical systems and devices without alteration of the lens or mirror; or
(ii) The receipt, possession, use or transfer of thorium or uranium contained in contact lenses, or in spectacles, or in eyepieces in binoculars or other optical instruments.
(f) Uranium contained in detector heads for use in fire detection units if each detector head contains 185 becquerels (0.005 microcuries) or less of uranium; or
(g) Thorium contained in any finished aircraft engine part containing nickel-thoria alloy if:
(i) The thorium is dispersed in the nickel-thoria alloy in the form of finely divided thoria (thorium dioxide); and
(ii) The thorium content in the nickel-thoria alloy is four percent or less by weight.
(4) The exemptions in subsection (3) of this section do not authorize the manufacture of any of the products described.
(5) No person may initially transfer for sale or distribution a product containing source material to persons exempt under this section, or equivalent regulations of an agreement state or the NRC, unless authorized by a license issued under 10 C.F.R. 40.52 to initially transfer such products for sale or distribution.
(a) Persons initially distributing source material in products covered by the exemptions in this section before August 27, 2013, without specific authorization may continue such distribution for one year beyond this date. Initial distribution may also be continued until NRC takes final action on a pending application for license or license amendment to specifically authorize distribution submitted no later than one year beyond this date.
(b) Persons authorized by an agreement state to manufacture, process, or produce these materials or products containing source material, and persons who import finished products or parts for sale or distribution must be authorized by a license issued under 10 C.F.R. 40.52 for distribution only and are exempt from the requirements of chapters 246-221 and 246-222 WAC, and WAC 246-235-020 (1) and (2).
[Statutory Authority: RCW 70.98.050 and 70.98.110. WSR 17-01-034, § 246-232-006, filed 12/12/16, effective 1/12/17; WSR 16-13-054, § 246-232-006, filed 6/10/16, effective 7/11/16. Statutory Authority: RCW 70.98.050. WSR 13-24-025, § 246-232-006, filed 11/22/13, effective 12/23/13. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 09-06-003, § 246-232-006, filed 2/18/09, effective 3/21/09. Statutory Authority: RCW 70.98.050. WSR 01-02-068, § 246-232-006, filed 12/29/00, effective 1/29/01.]



PDF246-232-007

Exemption of certain depleted uranium items.

(1) A person is exempt from the requirements for a license and from this chapter and chapters 246-233 and 246-235 WAC to the extent that the person receives, possesses, uses or transfers:
(a) Depleted uranium contained in counterweights installed in aircraft, rockets, projectiles and missiles, or stored or handled in connection with installation or removal of such counterweights if:
(i) Each counterweight has been impressed with the following legend clearly legible through any plating or other covering: "DEPLETED URANIUM"*;
(ii) Each counterweight is durably and legibly labeled or marked with the identification of the manufacturer and the statement: "UNAUTHORIZED ALTERATIONS PROHIBITED"*; and
(iii) The exemption contained in this subparagraph shall not be deemed to authorize the chemical, physical or metallurgical treatment or processing of any such counterweight other than repair or restoration of any plating or other covering.
*Note:
The requirements specified in (1)(a)(i) and (ii) of this subsection need not be met by counterweights manufactured prior to December 31, 1969, provided that such counterweights are impressed with the legend, "CAUTION - RADIOACTIVE MATERIAL - URANIUM," as previously required by the rules and were manufactured under a specific license issued by the Atomic Energy Commission and were impressed with the legend required by WAC 246-232-007 (1)(a)(i) in effect on June 30, 1969.
(b) Natural or depleted uranium used as shielding constituting part of any shipping container which is conspicuously and legibly impressed with the legend "CAUTION - RADIOACTIVE SHIELDING - URANIUM" and the uranium metal is encased in mild steel or in an equally fire resistant metal of a minimum wall thickness of 3.2 millimeters.
(2) The exemptions in this subsection do not authorize the manufacture of any of the products described.
[Statutory Authority: RCW 70.98.050 and 70.98.110. WSR 17-01-034, § 246-232-007, filed 12/12/16, effective 1/12/17; WSR 16-13-054, § 246-232-007, filed 6/10/16, effective 7/11/16. Statutory Authority: RCW 70.98.050. WSR 13-24-025, § 246-232-007, filed 11/22/13, effective 12/23/13; WSR 01-02-068, § 246-232-007, filed 12/29/00, effective 1/29/01.]



PDF246-232-008

Exemption of certain timepieces, hands or dials.

A person is exempt from the requirements for a license and from this chapter and chapters 246-233 and 246-235 WAC to the extent that the person receives, possesses, uses, transfers, owns or acquires, and does not apply radioactive material to, or incorporate radioactive material into, the following timepieces or hands or dials containing not more than the following specified quantities of radioactive material and not exceeding the following specified levels of radiation*:
*Note:
No person may introduce radioactive material into a product or material, knowing or having reason to believe that it will be transferred to persons exempt under this section or other sections or equivalent regulations of the NRC or an agreement state, except in accordance with a specific license issued by the NRC, Washington, D.C. 20555.
(1)(a) 925 megabecquerels (25 millicuries) of tritium per timepiece;
(b) 185 megabecquerels (5 millicuries) of tritium per hand;
(c) 555 megabecquerels (15 millicuries) of tritium per dial (bezels when used shall be considered as part of the dial);
(d) 3.7 megabecquerels (100 microcuries) of promethium-147 per watch or 7.4 megabecquerels (200 microcuries) of promethium-147 per any other timepiece;
(e) 740 kilobecquerels (20 microcuries) of promethium-147 per watch hand or 1.48 megabecquerels (40 microcuries) of promethium-147 per other timepiece hand;
(f) 2.22 megabecquerels (60 microcuries) of promethium-147 per watch dial or 4.44 megabecquerels (120 microcuries) of promethium-147 per other timepiece dial (bezels when used shall be considered as part of the dial);
(2) The levels of radiation from hands and dials containing promethium-147 will not exceed, when measured through 50 milligrams per square centimeter of absorber:
(a) For wrist watches, 1 microgray (0.1 millirad) per hour at 10 centimeters from any surface;
(b) For pocket watches, 1 microgray (0.1 millirad) per hour at 1 centimeter from any surface;
(c) For any other timepiece, 2 micrograys (0.2 millirad) per hour at 10 centimeters from any surface.
(3) 37 kilobecquerels (1 microcurie) of radium-226 per timepiece in intact timepieces manufactured prior to November 30, 2007.
[Statutory Authority: RCW 70.98.050. WSR 13-24-025, § 246-232-008, filed 11/22/13, effective 12/23/13. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 09-06-003, § 246-232-008, filed 2/18/09, effective 3/21/09. Statutory Authority: RCW 70.98.050. WSR 01-02-068, § 246-232-008, filed 12/29/00, effective 1/29/01.]



PDF246-232-009

Exemption of certain items containing radioactive material.

A person is exempt from the requirements for a license and from this chapter and chapters 246-233 and 246-235 WAC to the extent the person receives, possesses, uses, transfers, owns or acquires, and does not apply radioactive material to, or incorporate radioactive material into, the following products:*
*Note:
No person may introduce radioactive material into a product or material, knowing or having reason to believe that it will be transferred to persons exempt under this section or other sections or equivalent regulations of the NRC or an agreement state, except in accordance with a specific license issued by the NRC, Washington, D.C. 20555.
(1) Static elimination devices which contain, as a sealed source or sources, by-product material consisting of a total of not more than 18.5 MBq (500 microcuries) of Po-210 per device.
(2)(a) Ion generating tubes designed for ionization of air that contain, as a sealed source or sources, by-product material consisting of a total of not more than 18.5 MBq (500 microcuries) of Po-210 per device or a total of not more than 1.85 GBq (50 millicuries) of hydrogen-3 (tritium) per device.
(b) Such devices authorized before October 23, 2012, for use under the general license then provided in this section and equivalent regulations of an agreement state or the NRC, and manufactured, tested, and labeled by the manufacturer in accordance with the specifications contained in a specific license issued by the department, an agreement state, or the NRC.
(3) Balances of precision containing not more than 37 megabecquerels (1 millicurie) of tritium per balance or 18.5 megabecquerels (0.5 millicurie) of tritium per balance part manufactured before December 17, 2007.
(4) Marine compasses containing not more than 27.8 gigabecquerels (750 millicuries) of tritium gas and other marine navigational instruments containing not more than 9.25 gigabecquerels (250 millicuries) of tritium gas manufactured before December 17, 2007.
(5) Ionization chamber smoke detectors containing not more than 37 kilobecquerels (1 microcurie) of americium-241 per detector in the form of a foil and designed to protect life and property from fires.
(6) Electron tubes* provided that each tube contains no more than one of the following specified quantities of radioactive material and the levels of radiation from each electron tube do not exceed 10 micrograys (1 millirad) per hour at 1 centimeter from any surface when measured through 7 milligrams per square centimeter of absorber:
(a) 5.55 gigabecquerels (150 millicuries) of tritium per microwave receiver protector tube or 370 megabecquerels (10 millicuries) of tritium per any other electron tube;
(b) 37 kilobecquerels (1 microcurie) of cobalt-60;
(c) 185 kilobecquerels (5 microcuries) of nickel-63;
(d) 1.11 megabecquerels (30 microcuries) of krypton-85;
(e) 185 kilobecquerels (5 microcuries) of cesium-137;
(f) 1.11 megabecquerels (30 microcuries) of promethium-147.
*Note:
For purposes of this subsection, "electron tubes" include spark gap tubes, power tubes, gas tubes including glow lamps, receiving tubes, microwave tubes, indicator tubes, pick-up tubes, radiation detection tubes, and any other completely sealed tube that is designed to conduct or control electrical currents.
(7) Ionizing radiation measuring instruments containing, for purposes of internal calibration or standardization, one or more sources of radioactive material, provided that:
(a) Each source contains not more than one exempt quantity set forth in WAC 246-232-120, Schedule B, exempt quantities of radioactive materials; and
(b) Each instrument contains no more than 10 exempt quantities. For purposes of this subsection, an instrument's source(s) may contain either one type or different types of radionuclides and an individual exempt quantity may be composed of fractional parts of one or more of the exempt quantities in WAC 246-232-120, Schedule B, exempt quantities of radioactive materials, provided that the sum of such fractions must not exceed unity.
(c) For purposes of this subsection, 1.85 kilobecquerels (0.05 microcurie) of americium-241 is considered an exempt quantity.
[Statutory Authority: RCW 70.98.050 and 70.98.110. WSR 17-01-034, § 246-232-009, filed 12/12/16, effective 1/12/17. Statutory Authority: RCW 70.98.050. WSR 13-24-025, § 246-232-009, filed 11/22/13, effective 12/23/13. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 09-06-003, § 246-232-009, filed 2/18/09, effective 3/21/09. Statutory Authority: RCW 70.98.050. WSR 01-02-068, § 246-232-009, filed 12/29/00, effective 1/29/01.]



PDF246-232-010

Exempt concentrations and exempt quantities.

This section shall not be deemed to authorize the import of radioactive material or products containing radioactive material.
(1) Exempt concentrations.
(a) Except as provided in (b) of this subsection, a person is exempt from the requirements for a license and from this chapter and chapters 246-233 and 246-235 WAC to the extent that the person receives, possesses, uses, transfers, owns or acquires, and does not apply radioactive material to, or incorporate radioactive material into, products or materials containing radioactive material in concentrations in excess of those in WAC 246-232-130, Schedule C, exempt concentrations.
(b) No person may introduce radioactive material into a product or material knowing, or having reason to believe, that it will be transferred to persons exempt under this section or equivalent regulations of the NRC or an agreement state, except in accordance with a specific license issued by the NRC, Washington, D.C. 20555.
(c) A manufacturer, processor, or producer of a product or material is exempt from the requirements for a license and from this chapter and chapters 246-233 and 246-235 WAC to the extent that this person transfers radioactive material contained in a product or material in concentrations not in excess of those specified in WAC 246-232-130, Schedule C, and introduced into the product or material by a licensee holding a specific license issued by the NRC expressly authorizing such manufacture or introduction. This exemption does not apply to the transfer of radioactive material contained in any food, beverage, cosmetic, drug, or other commodity or product designed for ingestion or inhalation by, or application to, a human being.
(2) Exempt quantities.
(a)(i) Except as provided in (b) through (d) of this subsection, any person is exempt from the requirements for a license and from this chapter and chapters 246-233 and 246-235 WAC to the extent that such person receives, possesses, uses, transfers, owns, or acquires, and does not apply radioactive material to, or incorporate radioactive material into, radioactive material in individual quantities, each of which does not exceed the applicable quantity set forth in WAC 246-232-120, Schedule B, exempt quantities of radioactive materials.
(ii) Any person who possesses radioactive material received or acquired under the general license is exempt from the requirements for a license set forth in chapters 246-333, 246-235 WAC, and this chapter to the extent that such person uses, transfers, or owns such radioactive material. Such exemption does not apply for Radium-226.
(b) This subsection does not authorize the production, packaging, repackaging, or transfer of radioactive material for the purposes of commercial distribution, or the incorporation of radioactive material into products intended for commercial distribution.
(c) No person may, for purposes of commercial distribution, transfer radioactive material in the individual quantities set forth in WAC 246-232-120, Schedule B, exempt quantities of radioactive materials, knowing or having reason to believe that such quantities of radioactive material will be transferred to persons exempt under this section or equivalent rules of the NRC or an agreement state, except in accordance with a specific license issued by the NRC, Washington, D.C. 20555.
(d) No person may, for purposes of producing an increased radiation level, combine quantities of radioactive material covered by this exemption so that the aggregate quantity exceeds the limits set forth in WAC 246-232-120, Schedule B, exempt quantities of radioactive materials, except for radioactive material combined within a device placed in use before May 3, 1999, or as otherwise permitted by these rules.
[Statutory Authority: RCW 70.98.050. WSR 15-06-015, § 246-232-010, filed 2/23/15, effective 3/26/15; WSR 13-24-025, § 246-232-010, filed 11/22/13, effective 12/23/13; WSR 01-02-068, § 246-232-010, filed 12/29/00, effective 1/29/01; WSR 98-13-037, § 246-232-010, filed 6/8/98, effective 7/9/98. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 91-15-112 (Order 184), § 246-232-010, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-232-010, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. WSR 87-01-031 (Order 2450), § 402-19-190, filed 12/11/86; WSR 83-19-050 (Order 2026), § 402-19-190, filed 9/16/83. Statutory Authority: RCW 70.98.050. WSR 81-01-011 (Order 1570), § 402-19-190, filed 12/8/80. Statutory Authority: RCW 70.98.080. WSR 79-12-073 (Order 1459), § 402-19-190, filed 11/30/79, effective 1/1/80. Formerly WAC 402-20-190.]



PDF246-232-011

Exemption of certain self-luminous products containing radioactive material(s).

(1) Hydrogen-3 (tritium), krypton-85, or promethium-147.
(a) A person is exempt from the requirements for a license and from this chapter and chapters 246-233 and 246-235 WAC to the extent that the person receives, possesses, uses, transfers, owns or acquires, and does not manufacture, process, produce, apply radioactive material to, incorporate radioactive material into, or initially transfer for sale or distribution, self-luminous products containing hydrogen-3 (tritium), krypton-85, or promethium-147 in self-luminous products manufactured, processed, produced, imported or initially transferred in accordance with a specific license issued by the NRC. The exemption in this subsection does not apply to hydrogen-3, (tritium), krypton-85, or promethium-147 used in products primarily for frivolous purposes or in toys or adornments.
(b) Any person who desires to manufacture, process, produce, or initially transfer for sale or distribution self-luminous products containing tritium (H-3), krypton-85 (Kr-85), or promethium-147 (Pm-147) for use under (a) of this subsection should apply for a license under 10 C.F.R. 32.22 and for a certificate of registration in accordance with WAC 246-235-108.
(2) No person may introduce radioactive material into a product or material knowing, or having reason to believe, that it will be transferred to persons exempt under this section or other sections or equivalent regulations of the NRC or an agreement state, except in accordance with a specific license issued by the NRC, Washington, D.C. 20555.
[Statutory Authority: RCW 70.98.050 and 70.98.110. WSR 17-01-034, § 246-232-011, filed 12/12/16, effective 1/12/17; WSR 16-13-054, § 246-232-011, filed 6/10/16, effective 7/11/16. Statutory Authority: RCW 70.98.050. WSR 13-24-025, § 246-232-011, filed 11/22/13, effective 12/23/13. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 09-06-003, § 246-232-011, filed 2/18/09, effective 3/21/09. Statutory Authority: RCW 70.98.050. WSR 01-02-068, § 246-232-011, filed 12/29/00, effective 1/29/01.]



PDF246-232-012

Exemption of certain gas and aerosol detectors containing radioactive material.

(1)(a) Except for persons who manufacture, process, produce, or initially transfer for sale or distribution gas and aerosol detectors containing radioactive material, any person is exempt from the requirements for a license and from this chapter and chapters 246-221, 246-222, 246-233, 246-235, 246-240, 246-243, and 246-244 WAC to the extent that the person receives, possesses, uses, transfers, owns or acquires radioactive material in gas and aerosol detectors designed to protect health, safety, or property, and manufactured, processed, produced, or initially transferred in accordance with a specific license issued under 10 C.F.R. 32.26 which authorizes the initial transfer of the product for use under this chapter. This exemption also covers gas and aerosol detectors manufactured or distributed before November 30, 2007, in accordance with a specific license issued by a state under provisions comparable to 10 C.F.R. 32.26 authorizing distribution to persons exempt from regulatory requirements.
(b) Any person who desires to manufacture, process, or produce gas and aerosol detectors containing radioactive material, or to initially transfer such products for use under this subsection should apply for a license under 10 C.F.R. 32.26 and for a certificate of registration in accordance with WAC 246-235-108.
(2) No person may introduce radioactive material into a product or material knowing, or having reason to believe, that it will be transferred to persons exempt under this section or other sections or equivalent regulations of the NRC or an agreement state, except in accordance with a specific license issued by the NRC, Washington, D.C. 20555.
[Statutory Authority: RCW 70.98.050 and 70.98.110. WSR 17-01-034, § 246-232-012, filed 12/12/16, effective 1/12/17; WSR 16-13-054, § 246-232-012, filed 6/10/16, effective 7/11/16. Statutory Authority: RCW 70.98.050. WSR 13-24-025, § 246-232-012, filed 11/22/13, effective 12/23/13; WSR 01-02-068, § 246-232-012, filed 12/29/00, effective 1/29/01.]



PDF246-232-014

Exemption of C-14 urea diagnostic capsules for human use.

(1) Except as provided in subsections (2) and (3) of this section, a person is exempt from the requirements for a license and from this chapter and chapters 246-233 and 246-235 WAC if the person receives, possesses, uses, transfers, owns, or acquires, and does not apply radioactive material to, or incorporate radioactive material into, capsules containing 37 kilobecquerels (1 microcurie) of carbon-14 urea (allowing for nominal variation that may occur during the manufacturing process) each, for "in-vivo" diagnostic use for humans.
(2) A person who desires to use the capsules for research involving human subjects must apply for and receive a specific license under chapters 246-240 and 246-235 WAC.
(3) A person who desires to manufacture, prepare, process, produce, package, repackage, or transfer for commercial distribution these capsules must do so in accordance with a specific license issued by the NRC, Washington, D.C. 20555.
(4) Nothing in this section relieves persons from complying with applicable United States Food and Drug Administration, federal, and state requirements governing receipt, administration, and use of drugs.
[Statutory Authority: RCW 70.98.050 and 70.98.110. WSR 16-13-054, § 246-232-014, filed 6/10/16, effective 7/11/16. Statutory Authority: RCW 70.98.050. WSR 13-24-025, § 246-232-014, filed 11/22/13, effective 12/23/13; WSR 06-05-019, § 246-232-014, filed 2/6/06, effective 3/9/06; WSR 01-02-068, § 246-232-014, filed 12/29/00, effective 1/29/01.]



PDF246-232-015

Certain industrial devices.

(1) Except for persons who manufacture, process, produce, or initially transfer for sale or distribution industrial devices containing radioactive material designed and manufactured for the purpose of detecting, measuring, gauging or controlling thickness, density, level, interface location, radiation, leakage, or qualitative or quantitative chemical composition, or for producing an ionized atmosphere, any person is exempt from the requirements for a license and from the regulations in chapters 246-222, 246-221, 246-232, 246-233, 246-235, 246-243, 246-240, and 246-244 WAC to the extent that such person receives, possesses, uses, transfers, owns, or acquires radioactive material, in these certain detecting, measuring, gauging, or controlling devices and certain devices for producing an ionized atmosphere, and manufactured, processed, produced, or initially transferred in accordance with a specific license issued under 10 C.F.R. 32.30 which authorizes the initial transfer of the device for use under this section. This exemption does not cover sources not incorporated into a device, such as calibration and reference sources.
(2) Any person who desires to manufacture, process, produce, or initially transfer for sale or distribution industrial devices containing radioactive material for use under subsection (1) of this section, should apply for a license under 10 C.F.R. 32.30 and for a certificate of registration in accordance with WAC 246-235-108.
[Statutory Authority: RCW 70.98.050 and 70.98.110. WSR 17-01-034, § 246-232-015, filed 12/12/16, effective 1/12/17; WSR 16-13-054, § 246-232-015, filed 6/10/16, effective 7/11/16.]



PDF246-232-020

Types of licenses.

Licenses for radioactive material are of two types: General and specific.
(1) A general license is provided by regulation and grants authority to a person for certain activities involving radioactive material, and is effective without filing an application with the department or issuance of licensing documents to a particular person. However, registration or the filing of a certificate with the department may also be required by the particular general license. The general licensee is subject to all other applicable rules and any limitations of the general license.
(2) The department issues a specific license to a named person, after review and approval of an application. The licensee is subject to all applicable rules, including chapter 246-235 WAC, Radioactive materials - Specific licenses, and any limitations specified in the specific license.
[Statutory Authority: RCW 70.98.050. WSR 13-24-025, § 246-232-020, filed 11/22/13, effective 12/23/13; WSR 04-04-055, § 246-232-020, filed 1/30/04, effective 3/1/04. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 91-15-112 (Order 184), § 246-232-020, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-232-020, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. WSR 79-12-073 (Order 1459), § 402-19-220, filed 11/30/79, effective 1/1/80. Formerly WAC 402-20-020.]



PDF246-232-030

Prelicensing inspection.

The department may verify information contained in applications and secure additional information deemed necessary to make a reasonable determination as to whether to issue a license and whether any special conditions should be attached thereto by visiting the facility or location where radioactive materials would be possessed or used, and by discussing details of the proposed possession or use of the radioactive materials with the applicant or representatives designated by the applicant. Such visits may be made by the department or its duly authorized representatives.
[Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-232-030, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. WSR 79-12-073 (Order 1459), § 402-19-240, filed 11/30/79, effective 1/1/80. Formerly WAC 402-20-200.]



PDF246-232-040

Reciprocal recognition of licenses.

Before radioactive material can be used at any temporary job site, the jurisdictional status of the job site must be determined. Authorization for use of radioactive material at job sites under exclusive federal jurisdiction must be obtained from the appropriate regional office of the NRC, Washington, D.C. 20555. Before radioactive materials can be used as a temporary job site in another state, authorization must be obtained from that state if it is an agreement state, or from the NRC if it is a nonagreement state.
(1) A person authorized by a license issued by the NRC or an agreement state, may obtain authorization from the department to work in Washington state provided:
(a) The out-of-state license is issued by the NRC or agreement state with jurisdiction where the licensee maintains an office for directing the licensed work and for retaining radiation safety records;
(b) The out-of-state licensee must not possess or use radioactive materials or conduct authorized work in Washington state for more than one hundred eighty days in that twelve month period which starts the date approval is granted, and the appropriate fee is received by the department, as required in chapter 246-254 WAC;
(c) The out-of-state licensing document authorizes the work conducted;
(d) The licensed work is not conducted in an area under exclusive federal jurisdiction;
(e) The appropriate fee is currently paid, as required in chapter 246-254 WAC. Licensees send fees to Washington State Department of Health, Revenue Accounting, P.O. Box 1099, Olympia, Washington 98504-1099;
(f) The out-of-state licensee notifies the department in writing at least three days before each entry into Washington state to conduct licensed work.
(i) The written notification must be sent to the Radioactive Materials Section, Department of Health, P.O. Box 47827, Olympia, Washington 98504-7827. Fax, email, or other notifications may be approved by the department.
(ii) The written notification must include use and storage location(s), start and end dates of licensed work, and type of proposed possession and use in Washington state, and must include licensing documents authorizing the licensed work.
(iii) If an unexpected need or emergency means the three-day notice is impossible or would impose an undue hardship on the out-of-state licensee, the out-of-state licensee may telephone the department ( 360-236-3221), for permission to proceed immediately.
(iv) The department may waive the requirement for filing additional written notifications during the remainder of the twelve months following the receipt of the initial notification.
(g) The out-of-state licensee must:
(i) Comply with all terms and conditions of the licensing document issued by the licensing authority except such terms or conditions contrary to the requirements or rules of the department or this section;
(ii) Comply with all applicable rules, terms and conditions of the department; and
(iii) Promptly provide other information the department may request.
(h) The out-of-state licensee must request approval for changes in work locations, radioactive material, or work conducted if different from the most recent information provided to the department.
(i) The out-of-state licensee may not transfer or dispose of radioactive material except by transfer to a person specifically licensed by the department or by the NRC or an agreement state to receive such material.
(j) The out-of-state specific licensee may possess or use radioactive material or conduct authorized work in offshore waters for more than one hundred eighty days in any calendar year, if the specific license issued by an agreement state or the NRC authorizes the specific licensee to possess or use radioactive material or conduct authorized work in offshore waters for an unlimited period of time.
(2) A person who holds a specific license issued by the NRC or an agreement state authorizing the holder to manufacture, install, or service a device described in WAC 246-233-020 within the areas subject to the jurisdiction of the licensing body is hereby granted a general license to install and service such device in this state in areas not under exclusive federal jurisdiction provided:
(a) Such person must file a report with the department within thirty days after the end of each calendar quarter in which any device is transferred to or from, or installed in this state. Each report must identify each general licensee to or from whom such device is transferred by name and address, the device manufacturer (or initial transferor), model number and serial number, and the quantity and type of radioactive material contained in the device;
(b) The device has been, and is, manufactured, labeled, installed, and serviced in accordance with applicable provisions of the specific license issued to a person by the NRC or an agreement state;
(c) Such person must ensure that any labels required to be affixed to the device under rules of the authority which licensed the manufacture of the device bear a statement that removal of the label is prohibited; and
(d) The specific licensee must provide each general licensee to and from whom such device is transferred, or on whose premises such device is installed, a copy of the general license in WAC 246-233-020.
(3) The department may withdraw, limit, or qualify its acceptance of any specific license or equivalent licensing document issued by another agency, or any product distributed pursuant to such licensing document, upon determining that such action is necessary to prevent undue hazard to public health and safety, or to the environment, or to property.
[Statutory Authority: RCW 70.98.050. WSR 13-24-025, § 246-232-040, filed 11/22/13, effective 12/23/13; WSR 04-04-055, § 246-232-040, filed 1/30/04, effective 3/1/04; WSR 01-02-068, § 246-232-040, filed 12/29/00, effective 1/29/01; WSR 99-15-105, § 246-232-040, filed 7/21/99, effective 8/21/99; WSR 98-13-037, § 246-232-040, filed 6/8/98, effective 7/9/98. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 91-15-112 (Order 184), § 246-232-040, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-232-040, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. WSR 87-01-031 (Order 2450), § 402-19-250, filed 12/11/86; WSR 83-19-050 (Order 2026), § 402-19-250, filed 9/16/83. Statutory Authority: RCW 70.98.050. WSR 81-01-011 (Order 1570), § 402-19-250, filed 12/8/80. Statutory Authority: RCW 70.98.080. WSR 79-12-073 (Order 1459), § 402-19-250, filed 11/30/79, effective 1/1/80. Formerly WAC 402-20-210.]



PDF246-232-050

Terms and conditions of licenses.

(1) Each license issued pursuant to this part shall be subject to all the provisions of the act, as now or hereafter in effect, and to all rules, regulations, and orders of the department.
(2) No license issued or granted under chapters 246-232, 246-233, or 246-235 WAC and no right to possess or use radioactive material granted by any license issued pursuant to chapters 246-233 and 246-235 WAC shall be transferred, assigned, or in any manner disposed, either voluntarily or involuntarily, directly or indirectly, through transfer of control of any license to any person unless the department shall, after securing full information, find that the transfer is in accordance with the provisions of the act, and gives its consent in writing.
(3) Each person licensed by the department pursuant to chapters 246-233 and 246-235 WAC shall confine use and possession of the material licensed to the locations and purposes authorized by the license.
(4) Approval of licensee's procedures by the department does not release the licensee from responsibility if adherence to these procedures results in undue exposure to individuals or loss of control of radioactive material.
(5) Each specific licensee must notify the department of health, office of radiation protection, in writing, immediately following the filing of a voluntary or involuntary petition for bankruptcy under any chapter of Title 11 (Bankruptcy) of the United States Code by or against:
(a) The licensee;
(b) An entity (as the term is defined in 11 U.S.C. 101(15)) controlling the licensee or listing the license or licensee as property of the estate; or
(c) An affiliate (as the term is defined in 11 U.S.C. 101(2)) of the licensee.
(6) The specific licensee's bankruptcy notification must include:
(a) The bankruptcy court in which the petition for bankruptcy was filed;
(b) The date of the filing of the petition;
(c) A complete and detailed inventory of all radioactive material possessed under the license including nuclide, form, activity and planned disposition;
(d) An estimation of the type and quantities of radioactive material the licensee plans to continue to receive or use on a routine basis;
(e) A description of security and storage for the radioactive material currently possessed;
(f) A plan for radioactive waste disposal, the estimated completion date(s), and the cost;
(g) An evaluation of facility and equipment contamination, estimate of clean-up costs, and a decontamination plan which includes a thorough description of how the cleanup will be funded and how it will be accomplished;
(h) An organizational chart specifying sole owners, partnerships, or officers in the corporation who have legal and fiscal responsibilities for the licensee;
(i) A description of any other changes affecting the terms and conditions of the radioactive materials license.
(7) Each specific licensee must notify the department within five working days if any items in subsection (6) of this section change during bankruptcy proceedings.
(8) The department will consider clean-up costs as part of the licensee's administrative costs if decontamination is necessary to comply with these regulations;
(9) Each general licensee required to register by WAC 246-233-020 (3)(k) must notify the department of health, radiation protection, in writing, immediately following the filing of a voluntary or involuntary petition for bankruptcy under any chapter of Title 11 (Bankruptcy) of the United States Code by or against:
(a) The licensee;
(b) An entity (as that term is defined in 11 U.S.C. 101(15)) controlling the licensee or listing the license or licensee as property of the estate; or
(c) An affiliate (as that term is defined in 11 U.S.C. 101(2)) of the licensee.
(10) The general licensee's bankruptcy notification must include:
(a) The bankruptcy court in which the petition for bankruptcy was filed; and
(b) The date of the filing of the petition.
(11) For the purposes of this section, "affiliate" means:
(a) A person as defined in WAC 246-220-010 that directly or indirectly owns, controls, or holds with power to vote, twenty percent or more of the outstanding voting securities of the licensee (unless that person holds such securities (i) in a fiduciary or agency capacity without sole discretionary power to vote such securities, or (ii) solely to secure a debt, if such person has not in fact exercised such power to vote);
(b) A corporation, twenty percent or more of whose outstanding voting securities are directly or indirectly owned, controlled, or held with power to vote, by the licensee;
(c) A person whose business is operated under a lease or operating agreement by a licensee, or person substantially all of whose property is operated under an operating agreement with the licensee; or
(d) A person that operates the business or substantially all of the property of the licensee under a lease or operating agreement.
[Statutory Authority: RCW 70.98.050. WSR 13-24-025, § 246-232-050, filed 11/22/13, effective 12/23/13; WSR 04-04-055, § 246-232-050, filed 1/30/04, effective 3/1/04. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 92-06-008 (Order 245), § 246-232-050, filed 2/21/92, effective 3/23/92. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-232-050, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. WSR 87-01-031 (Order 2450), § 402-19-300, filed 12/11/86; WSR 83-19-050 (Order 2026), § 402-19-300, filed 9/16/83. Statutory Authority: RCW 70.98.050. WSR 81-01-011 (Order 1570), § 402-19-300, filed 12/8/80. Statutory Authority: RCW 70.98.080. WSR 79-12-073 (Order 1459), § 402-19-300, filed 11/30/79, effective 1/1/80.]



PDF246-232-060

Termination of licenses and decommissioning of sites and separate buildings or outdoor areas.

(1) Each specific licensee shall immediately notify the department in writing when the licensee decides to permanently discontinue all activities involving materials authorized under the license and request termination of the license. This notification and request for termination of the license must include the reports and information specified in subsection (3)(c) and (d) of this section. The licensee is subject to the provisions of subsections (3) and (4) of this section, as applicable.
(2) No less than thirty days before the expiration date specified in a specific license, the licensee shall either:
(a) Submit an application for license renewal under WAC 246-235-050; or
(b) Notify the department in writing if the licensee decides not to renew the license.
(3) If a specific licensee does not submit an application for license renewal under WAC 246-235-050, the licensee shall on or before the expiration date specified in the license:
(a) Terminate use of radioactive material;
(b) Properly dispose of radioactive material;
(c) Submit a completed departmental form "Certificate of disposition of radioactive material" or equivalent; and
(d) Submit a radiation survey report to confirm the absence of radioactive materials or establish the levels of radioactive contamination, unless the department determines a radiation survey report is not necessary.
(i) If no radioactive contamination attributable to activities conducted under the license is detected, the licensee shall submit a certification that no detectable radioactive contamination was found. If the information submitted under this paragraph and subsection (3)(c) and (d) of this section is adequate, the department will notify the licensee in writing that the license is terminated.
(ii) If detectable levels of radioactive contamination attributable to activities conducted under the license are found, the license continues in effect beyond the expiration date, if necessary, with respect to possession of residual radioactive material present as contamination until the licensee meets the criteria established in chapter 246-246 WAC and the department notifies the licensee in writing that the license is terminated. During this time, the licensee is subject to the provisions of subsection (4) of this section. In addition to the information submitted under subsection (3)(c) and (d) of this section, the licensee shall submit a plan for decontamination, if necessary.
(4) Each specific licensee who possesses residual radioactive material under subsection (3)(d)(ii) of this section, following the expiration of the license, shall:
(a) Be limited to actions, involving radioactive material related to decontamination and preparation for release in accordance with chapter 246-246 WAC; and
(b) Continue to control entry to restricted areas until:
(i) Such areas are suitable for release in accordance with chapter 246-246 WAC;
(ii) Contaminated equipment complies with guidance contained in WAC 246-232-140, Schedule D; and
(iii) The department notifies the licensee in writing that the license is terminated.
(5) Each general licensee licensed under the provisions of WAC 246-233-040, shall immediately notify the department in writing when the licensee decides to discontinue all activities involving radioactive materials authorized under the general license. Such notification shall include a description of how the generally licensed material was disposed and the results of facility surveys, if applicable, to confirm the absence of radioactive materials.
(6) Within sixty days of the occurrence of any of the following, each specific licensee shall provide notification to the department in writing of such occurrence, and either begin decommissioning its site, or any separate building or outdoor area that contains residual radioactivity so that the site, building, or outdoor area is suitable for release in accordance with chapter 246-246 WAC, or submit within twelve months of notification a decommissioning plan, if required by subsection (10)(a) of this section, and begin decommissioning upon approval of that plan if:
(a) The license has expired or has been revoked by the department; or
(b) The licensee has decided to permanently cease principal activities, as defined in this section, at the entire site or in any separate building or outdoor area that contains residual radioactivity such that the site, building, or outdoor area is unsuitable for release in accordance with chapter 246-246 WAC; or
(c) No principal activities under the license have been conducted for a period of twenty-four months; or
(d) No principal activities have been conducted for a period of twenty-four months in any separate building or outdoor area that contains residual radioactivity such that the building or outdoor area is unsuitable for release in accordance with chapter 246-246 WAC.
(7) As used in this section, principal activities means activities authorized by the license which are essential to achieving the purpose(s) for which the license was issued or amended. Storage during which no licensed material is accessed for use or disposal and activities incidental to decontamination or decommissioning are not principal activities.
(8) Coincident with the notification required by subsection (6) of this section, the licensee shall maintain in effect all decommissioning financial assurances established by the licensee pursuant to WAC 246-235-075 or as required by this section. The amount of the financial assurance must be increased, or may be decreased, as appropriate, to cover the detailed cost estimate for decommissioning established pursuant to subsection (10)(d)(v) of this section. Following approval of the decommissioning plan, a licensee may reduce the amount of the financial assurance as decommissioning proceeds and radiological contamination is reduced at the site with the approval of the department.
(9) The department may grant a request to extend the time periods established in subsection (6) of this section if the department determines that this relief is not detrimental to the public health and safety and is otherwise in the public interest. The request must be submitted no later than thirty days before notification pursuant to subsection (6) of this section. The schedule for decommissioning set forth in subsection (6) of this section may not commence until the department has made a determination on the request.
(10)(a) A decommissioning plan must be submitted if required by license condition or if the procedures and activities necessary to carry out decommissioning of the site or separate building or outdoor area have not been previously approved by the department and these procedures could increase potential health and safety impacts to workers or to the public, such as in any of the following cases:
(i) Procedures would involve techniques not applied routinely during cleanup or maintenance operations;
(ii) Workers would be entering areas not normally occupied where surface contamination and radiation levels are significantly higher than routinely encountered during operation;
(iii) Procedures could result in significantly greater airborne concentrations of radioactive materials than are present during operation; or
(iv) Procedures could result in significantly greater releases of radioactive material to the environment than those associated with operation.
(b) The department may approve an alternate schedule for submittal of a decommissioning plan required pursuant to subsection (6) of this section if the department determines that the alternative schedule is necessary to the effective conduct of decommissioning operations and presents no undue risk from radiation to the public health and safety and is otherwise in the public interest.
(c) Procedures such as those listed in (a) of this subsection with potential health and safety impacts may not be carried out prior to approval of the decommissioning plan.
(d) The proposed decommissioning plan for the site or separate building or outdoor area must include:
(i) A description of the conditions of the site or separate building or outdoor area sufficient to evaluate the acceptability of the plan;
(ii) A description of planned decommissioning activities;
(iii) A description of methods used to ensure protection of workers and the environment against radiation hazards during decommissioning;
(iv) A description of the planned final radiation survey;
(v) An updated detailed cost estimate for decommissioning, comparison of that estimate with present funds set aside for decommissioning, and a plan for assuring the availability of adequate funds for completion of decommissioning;
(vi) A description of the physical security plan and material control and accounting plan provisions in place during decommissioning;
(vii) For decommissioning plans calling for completion of decommissioning later than twenty-four months after plan approval, the plan shall include a justification for the delay based on the criteria in subsection (12) of this section.
(e) The proposed decommissioning plan will be approved by the department if the information therein demonstrates that the decommissioning will be completed as soon as practicable and that the health and safety of workers and the public will be adequately protected.
(11)(a) Except as provided in subsection (12) of this section, licensees shall complete decommissioning of the site or separate building or outdoor area as soon as practicable but no later than twenty-four months following the initiation of decommissioning.
(b) Except as provided in subsection (12) of this section, when decommissioning involves the entire site, the licensee shall request license termination as soon as practicable but no later than twenty-four months following the initiation of decommissioning.
(12) The department may approve a request for an alternative schedule for completion of decommissioning of the site or separate building or outdoor area, and license termination if appropriate, if the department determines that the alternative is warranted by consideration of the following:
(a) Whether it is technically feasible to complete decommissioning within the allotted twenty-four-month period;
(b) Whether sufficient waste disposal capacity is available to allow completion of decommissioning within the allotted twenty-four-month period;
(c) Whether a significant volume reduction in wastes requiring disposal will be achieved by allowing short-lived radionuclides to decay;
(d) Whether a significant reduction in radiation exposure to workers can be achieved by allowing short-lived radionuclides to decay; and
(e) Other site-specific factors which the department may consider appropriate on a case-by-case basis, such as the regulatory requirements of other government agencies, lawsuits, groundwater treatment activities, monitored natural groundwater restoration, actions that could result in more environmental harm than deferred cleanup, and other factors beyond the control of the licensee.
(13) As the final step in decommissioning, the licensee shall:
(a) Certify the disposition of all licensed material, including accumulated wastes, by submitting a completed certificate of disposition of radioactive material or equivalent information; and
(b) Conduct a radiation survey of the premises where the licensed activities were carried out and submit a report of the results of this survey, unless the licensee demonstrates in some other manner that the premises are suitable for release in accordance with the criteria for decommissioning in chapter 246-246 WAC. The licensee shall, as appropriate:
(i) Report levels of gamma radiation in units of millisieverts (microroentgen) per hour at one meter from surfaces, and report levels of radioactivity, including alpha and beta, in units of megabecquerels (disintegrations per minute or microcuries) per one hundred square centimeters—removable and fixed—for surfaces, megabecquerels (microcuries) per milliliter for water, and becquerels (picocuries) per gram for solids such as soils or concrete; and
(ii) Specify the survey instrument(s) used and certify that each instrument is properly calibrated and tested.
(14) Specific licenses, including expired licenses, will be terminated by written notice to the licensee when the department determines that:
(a) Radioactive material has been properly disposed;
(b) Reasonable effort has been made to eliminate residual radioactive contamination, if present; and
(c)(i) A radiation survey has been performed which demonstrates that the premises are suitable for release in accordance with the criteria for decommissioning in chapter 246-246 WAC; or
(ii) Other information submitted by the licensee is sufficient to demonstrate that the premises are suitable for release in accordance with the criteria for decommissioning in chapter 246-246 WAC; and
(d) Records required by subsections (16) and (18) of this section have been received.
(15) Specific licenses for uranium and thorium milling are exempt from subsections (6)(d), (9) and (10) of this section with respect to reclamation of tailings impoundments or waste disposal areas.
(16) Prior to license termination, each licensee authorized to possess radioactive material with a half-life greater than one hundred twenty days, in an unsealed form, shall forward the following records to the department:
(a) Records of disposal required by WAC 246-221-230 (8)(a); and
(b) Records of results required by WAC 246-221-230 (7)(h).
(17) If licensed activities are transferred or assigned in accordance with WAC 246-232-050(2), each licensee authorized to possess radioactive material, with a half-life greater than one hundred twenty days, in an unsealed form, shall transfer the following records to the new licensee and the new licensee will be responsible for maintaining these records until the license is terminated:
(a) Records of disposal required by WAC 246-221-230 (8)(a); and
(b) Records of results required by WAC 246-221-230 (7)(h).
(18) Prior to license termination, each licensee shall forward the records required by WAC 246-235-075(6) to the department.
[Statutory Authority: RCW 70.98.050. WSR 13-24-025, § 246-232-060, filed 11/22/13, effective 12/23/13; WSR 04-04-055, § 246-232-060, filed 1/30/04, effective 3/1/04; WSR 00-07-085, § 246-232-060, filed 3/15/00, effective 4/15/00; WSR 99-15-105, § 246-232-060, filed 7/21/99, effective 8/21/99. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 97-08-095, § 246-232-060, filed 4/2/97, effective 5/3/97; WSR 91-15-112 (Order 184), § 246-232-060, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-232-060, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. WSR 83-19-050 (Order 2026), § 402-19-330, filed 9/16/83.]



PDF246-232-070

Modification and revocation of licenses.

(1) The terms and conditions of all licenses shall be subject to amendment, revision, or modification, or the license may be suspended or revoked by reason of amendments to the act, or by reason of rules, regulations, and orders issued by the department.
(2) Any license may be revoked, suspended, or modified, in whole or in part, for any material false statement in the application or any statement of fact required under provisions of the act, or because of conditions revealed by such application or statement of fact or any report, record, or inspection or other means which would warrant the department to refuse to grant a license on an original application, or for violation of, or failure to observe any of the terms and conditions of the act, or of the license, or of any rule, regulation, or order of the department.
(3) Except in cases of willful disregard for the regulations or applicable license conditions or those in which the public health, interest, or safety requires otherwise, no license shall be modified, suspended, or revoked unless, prior to the institution of proceedings therefore, facts or conduct which may warrant such action shall have been called to the attention of the licensee in writing and the licensee shall have been accorded an opportunity to demonstrate or achieve compliance with all lawful requirements.
[Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-232-070, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. WSR 87-01-031 (Order 2450), § 402-19-350, filed 12/11/86; WSR 83-19-050 (Order 2026), § 402-19-350, filed 9/16/83; WSR 79-12-073 (Order 1459), § 402-19-350, filed 11/30/79, effective 1/1/80. Formerly WAC 402-20-180.]



PDF246-232-080

Transfer of material.

(1) No licensee shall transfer radioactive material except as authorized pursuant to this section.
(2) Except as otherwise provided in the license and subject to the provisions of this section, a licensee may transfer radioactive material:
(a) To the department. A licensee may transfer material to the department only after receiving prior approval from the department;
(b) To the United States Department of Energy;
(c) To a person exempt from the rules in this part to the extent permitted under such exemption;
(d) To a person authorized to receive such material under terms of a general license or its equivalent, or a specific license or equivalent licensing document, issued by the department, the NRC or an agreement state, or to a person otherwise authorized to receive such material by the federal government or an agency thereof, the department, or an agreement state; or
(e) As otherwise authorized by the department in writing.
(3) Before transferring radioactive material to a specific licensee of the department, the NRC or an agreement state, or to a general licensee who is required to register with the department, the NRC or an agreement state prior to receipt of the radioactive material, the licensee transferring the material must verify that the transferee's license authorizes the receipt of the type, form, and quantity of radioactive material to be transferred.
(4) The following methods for the verification required by subsection (3) of this section are acceptable:
(a) The transferor may obtain for possession, and read, a current copy of the transferee's specific license or registration certificate;
(b) The transferor may obtain for possession a written certification from the transferee that the transferee is authorized by license or registration certificate to receive the type, form, and quantity of radioactive material to be transferred, specifying the license or registration certificate number, issuing agency, and expiration date;
(c) For emergency shipments the transferor may accept oral certification by the transferee that the transferee is authorized by license or registration certificate to receive the type, form, and quantity of radioactive material to be transferred, specifying the license or registration certificate number, issuing agency, and expiration date: Provided, That the oral certification is confirmed in writing within ten days;
(d) The transferor may obtain other sources of information compiled by a reporting service from official records of the department, the NRC or the licensing agency of an agreement state as to the identity of licensees and the scope and expiration dates of licenses and registration; or
(e) When none of the methods of verification described in subsection (4) of this section are readily available or when a transferor desires to verify that information received by one of such methods is correct or up-to-date, the transferor may obtain and record confirmation from the department, the NRC or the licensing agency of an agreement state that the transferee is licensed to receive the radioactive material.
(5) Preparation for shipment and transport of radioactive material must be in accordance with the provisions of WAC 246-232-090.
(6) The requirements of subsection (4) of this section notwithstanding, no verification is required when returning used, unused or decayed sources of radiation to the original manufacturer, (e.g., industrial radiography sources, high dose-rate afterloader sources, teletherapy sources, portable moisture/density gauge sources, fixed gauge sources, and Mo-99/Tc-99m or Rb-82/Sr-82 generators).
[Statutory Authority: RCW 70.98.050. WSR 13-24-025, § 246-232-080, filed 11/22/13, effective 12/23/13. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 91-15-112 (Order 184), § 246-232-080, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-232-080, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. WSR 87-01-031 (Order 2450), § 402-19-400, filed 12/11/86. Statutory Authority: RCW 70.98.050. WSR 81-01-011 (Order 1570), § 402-19-400, filed 12/8/80. Statutory Authority: RCW 70.98.080. WSR 79-12-073 (Order 1459), § 402-19-400, filed 11/30/79, effective 1/1/80. Formerly WAC 402-20-170.]



PDF246-232-090

Transportation.

No person shall deliver radioactive material to a carrier for transport or transport radioactive material except as authorized in a general or specific license issued by the department or as exempted in chapter 246-231 WAC. General licenses for transportation of radioactive material and other transportation requirements are found in chapter 246-231 WAC.
[Statutory Authority: RCW 70.98.050. WSR 99-15-105, § 246-232-090, filed 7/21/99, effective 8/21/99. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 91-15-112 (Order 184), § 246-232-090, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-232-090, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. WSR 83-19-050 (Order 2026), § 402-19-500, filed 9/16/83. Statutory Authority: RCW 70.98.050. WSR 81-01-011 (Order 1570), § 402-19-500, filed 12/8/80. Statutory Authority: RCW 70.98.080. WSR 79-12-073 (Order 1459), § 402-19-500, filed 11/30/79, effective 1/1/80. Formerly WAC 402-20-220.]



PDF246-232-120

Schedule B, exempt quantities of radioactive materials.

(See also WAC 246-232-010(2).)
Radioactive Material
Microcuries
Antimony-122 (Sb-122)
100
Antimony-124 (Sb-124)
10
Antimony-125 (Sb-125)
10
Arsenic-73 (As-73)
100
Arsenic-74 (As-74)
10
Arsenic-76 (As-76)
10
Arsenic-77 (As-77)
100
Barium-131 (Ba-131)
10
Barium-133 (Ba-133)
10
Barium-140 (Ba-140)
10
Bismuth-210 (Bi-210)
1
Bromine-82 (Br-82)
10
Cadmium-109 (Cd-109)
10
Cadmium-115m (Cd-115m)
10
Cadmium-115 (Cd-115)
100
Calcium-45 (Ca-45)
10
Calcium-47 (Ca-47)
10
Carbon-14 (C-14)
100
Cerium-141 (Ce-141)
100
Cerium-143 (Ce-143)
100
Cerium-144 (Ce-144)
1
Cesium-129 (Cs-129)
100
Cesium-131 (Cs-131)
1,000
Cesium-134m (Cs-134m)
100
Cesium-134 (Cs-134)
1
Cesium-135 (Cs-135)
10
Cesium-136 (Cs-136)
10
Cesium-137 (Cs-137)
10
Chlorine-36 (Cl-36)
10
Chlorine-38 (Cl-38)
10
Chromium-51 (Cr-51)
1,000
Cobalt-57 (Co-57)
100
Cobalt-58m (Co-58m)
10
Cobalt-58 (Co-58)
10
Cobalt-60 (Co-60)
1
Copper-64 (Cu-64)
100
Dysprosium-165 (Dy-165)
10
Dysprosium-166 (Dy-166)
100
Erbium-169 (Er-169)
100
Erbium-171 (Er-171)
100
Europium-152 (Eu-152) 9.2h
100
Europium-152 (Eu-152) 13 yr
1
Europium-154 (Eu-154)
1
Europium-155 (Eu-155)
10
Fluorine-18 (F-18)
1,000
Gadolinium-153 (Gd-153)
10
Gadolinium-159 (Gd-159)
100
Gallium-67 (Ga-67)
100
Gallium-72 (Ga-72)
10
Germanium-68 (Ge-68)
10
Germanium-71 (Ge-71)
100
Gold-195 (Au-195)
10
Gold-198 (Au-198)
100
Gold-199 (Au-199)
100
Hafnium-181 (Hf-181)
10
Holmium-166 (Ho-166)
100
Hydrogen-3 (H-3)
1,000
Indium-111 (In-111)
100
Indium-113m (In-113m)
100
Indium-114m (In-114m)
10
Indium-115m (In-115m)
100
Indium-115 (In-115)
10
Iodine-123 (I-123)
100
Iodine-125 (I-125)
1
Iodine-126 (I-126)
1
Iodine-129 (I-129)
0.1
Iodine-131 (I-131)
1
Iodine-132 (I-132)
10
Iodine-133 (I-133)
1
Iodine-134 (I-134)
10
Iodine-135 (I-135)
10
Iridium-192 (Ir-192)
10
Iridium-194 (Ir-194)
100
Iron-52 (Fe-52)
10
Iron-55 (Fe-55)
100
Iron-59 (Fe-59)
10
Krypton-85 (Kr-85)
100
Krypton-87 (Kr-87)
10
Lanthanum-140 (La-140)
10
Lutetium-177 (Lu-177)
100
Manganese-52 (Mn-52)
10
Manganese-54 (Mn-54)
10
Manganese-56 (Mn-56)
10
Mercury-197m (Hg-197m)
100
Mercury-197 (Hg-197)
100
Mercury-203 (Hg-203)
10
Molybdenum-99 (Mo-99)
100
Neodymium-147 (And-147)
100
Neodymium-149 (And-149)
100
Nickel-59 (Ni-59)
100
Nickel-63 (Ni-63)
10
Nickel-65 (Ni-65)
100
Niobium-93m (Nb-93m)
10
Niobium-95 (Nb-95)
10
Niobium-97 (Nb-97)
10
Osmium-185 (So-185)
10
Osmium-191m (So-191m)
100
Osmium-191 (Os-191)
100
Osmium-193 (Os-193)
100
Palladium-103 (Pd-103)
100
Palladium-109 (Pd-109)
100
Phosphorus-32 (P-32)
10
Platinum-191 (Pt-191)
100
Platinum-193m (Pt-193m)
100
Platinum-193 (Pt-193)
100
Platinum-197m (Pt-197m)
100
Platinum-197 (Pt-197)
100
Polonium-210 (Po-210)
0.1
Potassium-42 (K-42)
10
Potassium-43 (K-43)
10
Praseodymium-142 (Pr-142)
100
Praseodymium-143 (Pr-143)
100
Promethium-147 (Pm-147)
10
Promethium-149 (Pm-149)
10
Radium-226 (Ra-226)
0.1
Rhenium-186 (Re-186)
100
Rhenium-188 (Re-188)
100
Rhodium-103m (Rh-103m)
100
Rhodium-105 (Rh-105)
100
Rubidium-81 (Rb-81)
10
Rubidium-86 (Rb-86)
10
Rubidium-87 (Rb-87)
10
Ruthenium-97 (Ru-97)
100
Ruthenium-103 (Ru-103)
10
Ruthenium-105 (Ru-105)
10
Ruthenium-106 (Ru-106)
1
Samarium-151 (Sm-151)
10
Samarium-153 (Sm-153)
100
Scandium-46 (Sc-46)
10
Scandium-47 (Sc-47)
100
Scandium-48 (Sc-48)
10
Selenium-75 (Se-75)
10
Silicon-31 (Si-31)
100
Silver-105 (Ag-105)
10
Silver-110m (Ag-110m)
1
Silver-111 (Ag-111)
100
Sodium-22 (Na-22)
10
Sodium-24 (Na-24)
10
Strontium-85 (Sr-85)
10
Strontium-89 (Sr-89)
1
Strontium-90 (Sr-90)
0.1
Strontium-91 (Sr-91)
10
Strontium-92 (Sr-92)
10
Sulphur-35 (S-35)
100
Tantalum-182 (Ta-182)
10
Technetium-96 (Tc-96)
10
Technetium-97m (Tc-97m)
100
Technetium-97 (Tc-97)
100
Technetium-99m (Tc-99m)
100
Technetium-99 (Tc-99)
10
Tellurium-125m (Te-125m)
10
Tellurium-127m (Te-127m)
10
Tellurium-127 (Te-127)
100
Tellurium-129m (Te-129m)
10
Tellurium-129 (Te-129)
100
Tellurium-131m (Te-131m)
10
Tellurium-132 (Te-132)
10
Terbium-160 (Tb-160)
10
Thallium-200 (Tl-200)
100
Thallium-201 (Tl-201)
100
Thallium-202 (Tl-202)
100
Thallium-204 (Tl-204)
10
Thulium-170 (Tm-170)
10
Thulium-171 (Tm-171)
10
Tin-113 (Sn-113)
10
Tin-125 (Sn-125)
10
Tungsten-181 (W-181)
10
Tungsten-185 (W-185)
10
Tungsten-187 (W-187)
100
Vanadium-48 (V-48)
10
Xenon-131m (Xe-131m)
1,000
Xenon-133 (Xe-133)
100
Xenon-135 (Xe-135)
100
Ytterbium-169 (Yb-169)
10
Ytterbium-175 (Yb-175)
100
Yttrium-87 (Y-87)
10
Yttrium-88 (Y-88)
10
Yttrium-90 (Y-90)
10
Yttrium-91 (Y-91)
10
Yttrium-92 (Y-92)
100
Yttrium-93 (Y-93)
100
Zinc-65 (Zn-65)
10
Zinc-69m (Zn-69m)
100
Zinc-69 (Zn-69)
1,000
Zirconium-93 (Zr-93)
10
Zirconium-95 (Zr-95)
10
Zirconium-97 (Zr-97)
10
Any radioactive material not listed above other than alpha emitting radioactive material
0.1
[Statutory Authority: RCW 70.98.050 and 70.98.110. WSR 16-13-054, § 246-232-120, filed 6/10/16, effective 7/11/16. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 09-06-003, § 246-232-120, filed 2/18/09, effective 3/21/09. Statutory Authority: RCW 70.98.050. WSR 01-02-068, § 246-232-120, filed 12/29/00, effective 1/29/01. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 91-15-112 (Order 184), § 246-232-120, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-232-120, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. WSR 83-19-050 (Order 2026), § 402-19-550, filed 9/16/83; WSR 79-12-073 (Order 1459), § 402-19-550, filed 11/30/79, effective 1/1/80. Formerly WAC 402-20-240.]



PDF246-232-130

Schedule C, exempt concentrations.

(See WAC 246-232-010(1).)
Element (atomic
number)
Radionuclide
Column I
Gas
concentration
µCi/ml1
Column II
Liquid
and
solid
concentration
µCi/ml2
Antimony (51)
Sb-122
 
3x10-4
Sb-124
 
2x10-4
Sb-125
 
1x10-3
Argon (18)
Ar-37
1x10-3
 
Ar-41
4x10-7
 
Arsenic (33)
As-73
 
5x10-3
As-74
 
5x10-4
As-76
 
2x10-4
As-77
 
8x10-4
Barium (56)
Ba-131
 
2x10-3
Ba-140
 
3x10-4
Beryllium (4)
Be-7
 
2x10-2
Bismuth (83)
Bi-206
 
4x10-4
Bromine (35)
Br-82
4x10-7
3x10-3
Cadmium (48)
Cd-109
 
2x10-3
Cd-115m
 
3x10-4
Cd-115
 
3x10-4
Calcium (20)
Ca-45
 
9x10-5
Ca-47
 
5x10-4
Carbon (6)
C-14
1x10-6
8x10-3
Cerium (58)
Ce-141
 
9x10-4
Ce-143
 
4x10-4
Ce-144
 
1x10-4
Cesium (55)
Cs-131
 
2x10-2
Cs-134m
 
6x10-2
Cs-134
 
9x10-5
Chlorine (17)
Cl-38
9x10-7
4x10-3
Chromium (24)
Cr-51
 
2x10-2
Cobalt (27)
Co-57
 
5x10-3
Co-58
 
1x10-3
Co-60
 
5x10-4
Copper (29)
Cu-64
 
3x10-3
Dysprosium (66)
Dy-165
 
4x10-3
Dy-166
 
4x10-4
Erbium (68)
Er-169
 
9x10-4
Er-171
 
1x10-3
Europium (63)
Eu-152 (9.2 h)
 
6x10-4
 
Eu-155
 
2x10-3
Fluorine (9)
F-18
2x10-6
8x10-3
Gadolinium (64)
Gd-153
 
2x10-3
Gd-159
 
8x10-4
Gallium (31)
Ga-72
 
4x10-4
Germanium (32)
Ge-71
 
2x10-2
Gold (79)
Au-196
 
2x10-3
Au-198
 
5x10-4
Au-199
 
2x10-3
Hafnium (72)
Hf-181
 
7x10-4
Hydrogen (1)
H-3
5x10-6
3x10-2
Indium (49)
In-113m
 
1x10-2
In-114m
 
2x10-4
Iodine (53)
I-125
3x10-9
2x10-5
I-126
3x10-9
2x10-5
I-131
3x10-9
2x10-5
I-132
8x10-8
6x10-4
I-133
1x10-8
7x10-5
I-134
2x10-7
1x10-3
Iridium (77)
Ir-190
 
2x10-3
Ir-192
 
4x10-4
Ir-194
 
3x10-4
Iron (26)
Fe-55
 
8x10-3
Fe-59
 
6x10-4
Krypton (36)
Kr-85m
1x10-6
 
Kr-85
 
3x10-6
Lanthanum (57)
La-140
 
2x10-4
Lead (82)
Pb-203
 
4x10-3
Lutetium (71)
Lu-177
 
1x10-3
Manganese (25)
Mn-52
 
3x10-4
Mn-54
 
1x10-3
Mn-56
 
1x10-3
Mercury (80)
Hg-197m
 
2x10-3
Hg-197
 
3x10-3
Hg-203
 
2x10-4
Molybdenum (42)
Mo-99
 
2x10-3
Neodymium (60)
Nd-147
 
6x10-4
Nd-149
 
3x10-3
Nickel (28)
Ni-65
 
1x10-3
Niobium (41)
Nb-95
 
1x10-3
Nb-97
 
9x10-3
Osmium (76)
Os-185
 
7x10-4
Os-191m
 
3x10-2
Os-191
 
2x10-3
Os-193
 
6x10-4
Palladium (46)
Pd-103
 
3x10-3
Pd-109
 
9x10-4
Phosphorus (15)
P-32
 
2x10-4
Platinum (78)
Pt-191
 
1x10-3
Pt-193m
 
1x10-2
Pt-197m
 
1x10-2
Pt-197
 
1x10-3
Potassium (19)
K-42
 
3x10-3
Praseodymium (59)
Pr-142
 
3x10-4
Pr-143
 
5x10-4
Promethium (61)
Pm-147
 
2x10-3
Pm-149
 
4x10-4
Radium (88)
Ra-226
 
1x10-7
Ra-228
 
3x10-7
Rhenium (75)
Re-183
 
6x10-3
Re-186
 
9x10-4
Re-188
 
6x10-4
Rhodium (45)
Rh-103m
 
1x10-1
Rh-105
 
1x10-3
Rubidium (37)
Rb-86
 
7x10-4
Ruthenium (44)
Ru-97
 
4x10-3
Ru-103
 
8x10-4
Ru-105
 
1x10-3
Ru-106
 
1x10-4
Samarium (62)
Sm-153
 
8x10-4
Scandium (21)
Sc-46
 
4x10-4
Sc-47
 
9x10-4
Sc-48
 
3x10-4
Selenium (34)
Se-75
 
3x10-3
Silicon (14)
Si-31
 
9x10-3
Silver (47)
Ag-105
 
1x10-3
Ag-110m
 
3x10-4
Ag-111
 
4x10-4
Sodium (11)
Na-24
 
2x10-3
Strontium (38)
Sr-85
 
1x10-3
Sr-89
 
1x10-4
Sr-91
 
7x10-4
Sr-92
 
7x10-4
Sulfur (16)
S-35
9x10-8
6x10-4
Tantalum (73)
Ta-182
 
4x10-4
Technetium (43)
Tc-96m
 
1x10-1
Tc-96
 
1x10-3
Tellurium (52)
Te-125m
 
2x10-3
Te-127m
 
6x10-4
Te-127
 
3x10-3
Te-129m
 
3x10-4
Te-131m
 
6x10-4
Te-132
 
3x10-4
Terbium (65)
Tb-160
 
4x10-4
Thallium (81)
Tl-200
 
4x10-3
Tl-201
 
3x10-3
Tl-202
 
1x10-3
Tl-204
 
1x10-3
Thulium (69)
Tm-170
 
5x10-4
Tm-171
 
5x10-3
Tin (50)
Sn-113
 
9x10-4
Sn-125
 
2x10-4
Tungsten
(Wolfram) (74)
W-181
 
4x10-3
W-187
 
7x10-4
Vanadium (23)
V-48
 
3x10-4
Xenon (54)
Xe-131m
4x10-6
 
Xe-133
3x10-6
 
Xe-135
1x10-6
 
Ytterbium (70)
Yb-175
 
1x10-3
Yttrium (39)
Y-90
 
2x10-4
Y-91m
 
3x10-2
Y-91
 
3x10-4
Y-92
 
6x10-4
Y-93
 
3x10-4
Zinc (30)
Zn-65
 
1x10-3
Zn-69m
 
7x10-4
Zn-69
 
2x10-2
Zirconium (40)
Zr-95
 
6x10-4
Zr-97
 
2x10-4
Beta or gamma emitting radioactive material not listed above with half-life less than 3 years
 
1x10-10
1x10-6
Notes:
1 Values are given in Column I only for those materials normally used as gases
 
2 µCi/gm for solids
Note 1:
Many radionuclides decay into nuclides which are also radioactive. In expressing the concentrations in Schedule C the activity stated is that of the parent nuclide and takes into account the daughters.
Note 2:
For purposes of WAC 246-232-010(1) where there is involved a combination of nuclides, the limit for the combination should be derived as follows: Determine for each nuclide in the product the ratio between the concentration present in the product and the exempt concentration established in Schedule C for the specific nuclide when not in combination. The sum of such ratios may not exceed "1" (i.e., unity).
Example:
 
 
Concentration of Nuclide A in Product
 
Exempt concentration of Nuclide A
 
+
 
Concentration of Nuclide B in Product
 
Exempt concentration of Nuclide B
 
≤ 1
Note 3:
For the purpose of determining concentration in a product or device, the total quantity of radioactive material present is divided by only that weight or volume of the discrete part or component throughout which the radioactive material is relatively uniformly distributed. If the weight or volume of this part or component cannot be determined then the product or device should be evaluated on the basis of the total quantity of radioactive material present.
[Statutory Authority: RCW 70.98.050 and 70.98.110. WSR 16-13-054, § 246-232-130, filed 6/10/16, effective 7/11/16. Statutory Authority: RCW 70.98.050. WSR 13-24-025, § 246-232-130, filed 11/22/13, effective 12/23/13; WSR 01-02-068, § 246-232-130, filed 12/29/00, effective 1/29/01. Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 91-15-112 (Order 184), § 246-232-130, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-232-130, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. WSR 87-01-031 (Order 2450), § 402-19-580, filed 12/11/86; WSR 83-19-050 (Order 2026), § 402-19-580, filed 9/16/83; WSR 79-12-073 (Order 1459), § 402-19-580, filed 11/30/79, effective 1/1/80. Formerly WAC 402-20-250.]



PDF246-232-140

Schedule D.

acceptable surface contamination levels
nuclides a
average b c f
maximum b d f
removable b e f
wipe limits
U-nat, U-235, U-238, and associated decay products
5,000 dpm/100 cm2
15,000 dpm/100 cm2
1,000 dpm α/100 cm2
Transuranics, Ra-226, Ra-228, Th-230, Th-228, Pa-231, Ac-227, I-125, I-129
100 dpm/100 cm2
300 dpm/100 cm2
20 dpm/100 cm2
Th-nat, Th-232, Sr-90, Ra-223, Ra-224, U-232, I-126, I-131, I-133
1000 dpm/100 cm2
3000 dpm/100 cm2
200 dpm/100 cm2
Beta-gamma emitters (nuclides with decay modes other than alpha emission or spontaneous fission) except SR-90 and others noted above
5000 dpm/100 cm2
15,000 dpm/100 cm2
1000 dpm βγ/100 cm2
 
 
A
Where surface contamination by both alpha- and beta-gamma-emitting nuclides exists, the limits established for alpha-and beta-gamma-emitting nuclides should apply independently.
B
As used in this table, dpm (disintegrations per minute) means the rate of emission by radioactive material as determined by correcting the counts per minute observed by an appropriate detector for background, efficiency, and geometric factors associated with the instrumentation.
C
Measurements of average contaminant should not be averaged over more than 1 square meter. For objects of less surface area, the average should be derived for each such object.
D
The maximum contamination level applies to an area of not more than 100 cm2.
E
The amount of removable radioactive material per 100 cm2 of surface area should be determined by wiping that area with dry filter or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency. When removable contamination on objects of less surface area is determined, the pertinent levels should be reduced proportionally and the entire surface should be wiped.
F
The average and maximum radiation levels associated with surface contamination resulting from beta-gamma emitters should not exceed 0.2 mrad/hr at 1 cm and 1.0 mrad/hr at 1 cm, respectively, measured through not more than 7 milligrams per square centimeter of total absorber.
[Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 09-06-003, § 246-232-140, filed 2/18/09, effective 3/21/09. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-232-140, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. WSR 87-01-031 (Order 2450), § 402-19-590, filed 12/11/86; WSR 83-19-050 (Order 2026), § 402-19-590, filed 9/16/83.]



PDF246-232-990

Fees.

Fees are required from all applicants, licensees, or registrants. Chapter 246-254 WAC specifies fees for users of radiation subject to regulation under chapters 246-220 through 246-255 WAC.
[Statutory Authority: RCW 70.98.050 and 70.98.080. WSR 91-15-112 (Order 184), § 246-232-990, filed 7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040. WSR 91-02-049 (Order 121), recodified as § 246-232-990, filed 12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. WSR 83-19-050 (Order 2026), § 402-19-370, filed 9/16/83; WSR 79-12-073 (Order 1459), § 402-19-370, filed 11/30/79, effective 1/1/80.]