43,753 sections across 2,186 Washington regulatory chapters.
R.246-229-246-229-0080 What are the requirements for bypassing safety interlocks?
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Bypassing a safety interlock or interlocks is allowed only if:(1) Authorized by the radiation safety committee and/or radiation safety officer;(2) Recorded in a permanent log and a notice posted at the accelerator control console; and(3) The bypass procedure is terminated as soon…
R.246-229-246-229-0090 What are the minimum requirements for particle accelerator use?
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The minimum requirements for the registrant to use a particle accelerator are to:(1) Register the accelerator with the department;(2) Submit plan review/shielding design to the department and receive written approval;(3) Train operators and users;(4) Complete a qualified expert's…
R.246-229-246-229-0100 What are the recordkeeping requirements for particle accelerator use?
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RecordsRetention timeOperator training and qualificationsTwo years past last employment/operationSafety and warning device checksTwo yearsArea radiation monitorsTwo years (if necessary)Instrumentation testsTwo yearsSmear resultsTwo years (if necessary)Qualified expert radiation p…
R.246-230-246-230-001 Authority, purpose, and scope.
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The requirements of this chapter are adopted pursuant to the provisions of chapter 70A.388 RCW. This chapter establishes radiation safety standards for the use of security screening systems that emit ionizing radiation to detect contraband under clothing and within body cavities …
R.246-230-246-230-005 Relationship to other regulations.
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In addition to the requirements established in this chapter, registrants shall also comply with applicable requirements including, but not limited to, the following:(1) Chapter 246-220 WAC;(2) Chapter 246-221 WAC;(3) Chapter 246-222 WAC; and(4) Chapter 246-224 WAC.[Statutory Auth…
R.246-230-246-230-010 Definitions.
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The definitions in this section apply throughout this chapter unless the context clearly indicates otherwise.(1) "ALARA" (as low as reasonably achievable or as low as is reasonably achievable) means making every reasonable effort to maintain exposures to radiation as far below th…
R.246-230-246-230-015 Registration.
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The owner or controller of the security screening system who is responsible for the safe operation of the security screening system shall register the security screening system facility and security screening system with the department in accordance with chapter 246-224 WAC.[Stat…
R.246-230-246-230-020 Security screening system requirements.
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(1) A security screening system must meet the definition of a general-use security screening system unless a variance, as outlined in WAC 246-230-090, is obtained from the department to operate a limited-use security screening system. If a security screening system is capable of …
R.246-230-246-230-025 Authorized use.
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(1) A security screening system may only be used to screen an individual who has been committed to a correctional facility or who has been presented for confinement in a jail or detention facility, and must not be used to screen such individuals who are:(a) Minors;(b) Pregnant or…
R.246-230-246-230-030 Operating requirements of security screening system.
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(1) Each operator of a security screening system shall complete radiation safety training prior to performing any security screening system operations. The registrant shall develop a training program in consultation with a qualified expert and must include, at a minimum:(a) Radia…
R.246-230-246-230-040 Dose limits.
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(1) The registrant shall confirm that the manufacturer of the security screening system has ensured that operating parameters are optimized for the best performance at the lowest dose.(2) The radiation dose delivered to an individual must be ALARA while meeting the required detec…
R.246-230-246-230-050 Requirements for tracking dosage.
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(1) The registrant must ensure a method is in place to track the dose of radiation an individual receives as a result of security screening. The registrant must track the dose of radiation an individual receives from security screening systems:(a) Per screening;(b) Per calendar y…
R.246-230-246-230-060 Information to be provided to scanned individuals.
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Prior to screening, the registrant must ensure that the individual is informed:(1) That the security screening system emits ionizing radiation;(2) That the security screening system meets all requirements of this chapter; and(3) Of any available alternative screening options.[Sta…
R.246-230-246-230-070 Radiation surveys.
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(1) Radiation surveys must be conducted by a qualified expert to verify:(a) Dose of radiation per screening and maximum allowable scans per year for any individual at stated dosage per screening;(b) Radiation leakage at the surface, within radiation screening zone, at operator po…
R.246-230-246-230-080 Records.
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The registrant must maintain the following records on-site and make them available to the department:(1) Training records for each operator must be maintained for five years. Training records must document:(a) Operator's name;(b) Date of training; and(c) Training curriculum provi…
R.246-230-246-230-090 Variance request.
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A registrant may submit a written request to the department for a variance from WAC 246-230-020(1). The registrant shall not use a security screening system on individuals until the department approves the variance request.(1) The written request must be addressed to: X-ray Super…
R.246-231-246-231-001 Purpose and scope.
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(1) This chapter establishes requirements for packaging, preparation for shipment, and transportation of radioactive material.(2) Licensees shall also comply with applicable requirements of NRC, DOT, the United States Postal Service1, and other requirements of Title 246 WAC.(3) T…
R.246-231-246-231-005 Requirement for license.
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No licensee 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, NRC or an agreement state, or as exempted in this chapter.[Statutory Authority: RCW 70.98.…
R.246-231-246-231-010 Definitions, abbreviations, and acronyms.
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The definitions, abbreviations, and acronyms in this section and in WAC 246-220-010 apply throughout this chapter unless the context clearly indicates otherwise. To ensure compatibility with international transportation standards, all limits in this chapter are given in terms of …
R.246-231-246-231-030 Transportation of licensed material.
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(1) Each licensee who transports licensed material outside the site of usage, as specified in the license issued by the department, NRC or an agreement state, or where transport is on public highways, or who delivers licensed material to a carrier for transport, shall comply with…
R.246-231-246-231-035 Deliberate misconduct.
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(1) For the purpose of this chapter, deliberate misconduct by a person means an intentional act or omission that the person knows:(a) Would constitute a violation of a requirement, procedure, instruction, contract, purchase order, or policy; or(b) Causes or would cause, if not de…
R.246-231-246-231-040 Exemptions.
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(1) Common and contract carriers, freight forwarders, warehouse workers, and the U.S. Postal Service are exempt from this chapter and chapters 246-232, 246-233, 246-235, 246-237, 246-240, 246-243, and 246-244 WAC to the extent that they transport or store radioactive material in …
R.246-231-246-231-050 General licenses for carriers.
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(1) A general license is hereby issued to any common or contract carrier not exempted under WAC 246-231-040 to receive, possess, transport and store radioactive material in the regular course of their carriage for another or storage incident thereto, provided the transportation a…
R.246-231-246-231-060 General license—NRC-approved package.
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(1) A general license is hereby issued to any licensee of the department, NRC, or an agreement state, to transport, or to deliver to a carrier for transport, licensed material in a package for which a license, certificate of compliance, or other approval has been issued by the NR…
R.246-231-246-231-090 General license—Use of foreign approved package.
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(1) A general license is issued to any licensee of the department, NRC, or an agreement state, to transport, or to deliver to a carrier for transport, licensed material in a package the design of which has been approved in a foreign national competent authority certificate that h…
R.246-231-246-231-094 General license—Fissile material.
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(1) A general license is issued to any licensee of the department, NRC, or an agreement state, to transport fissile material, or to deliver fissile material to a carrier for transport, if the material is shipped in accordance with this section. The fissile material need not be co…
R.246-231-246-231-096 General license—Plutonium-beryllium special form material.
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(1) A general license is issued to any licensee of the department, NRC, or an agreement state, to transport fissile material in the form of plutonium-beryllium (Pu-Be) special form sealed sources, or to deliver Pu-Be sealed sources to a carrier for transport, if the material is s…
R.246-231-246-231-098 External radiation standards for all packages.
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(1) Except as provided in subsection (2) of this section, each package of radioactive materials offered for transportation must be designed and prepared for shipment so that under conditions normally incident to transportation the radiation level does not exceed two mSv/hour (200…
R.246-231-246-231-100 Applicability of operating controls and procedures.
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A licensee subject to this chapter, who, under a general or specific license, transports licensed material or delivers licensed material to a carrier for transport, shall comply with the requirements of 10 C.F.R. 71 Subpart G, with the quality assurance requirements of 10 C.F.R. …
R.246-231-246-231-103 Assumptions as to unknown properties.
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When the isotopic abundance, mass, concentration, degree of irradiation, degree of moderation, or other pertinent property of fissile material in any package is not known, the licensee shall package the fissile material as if the unknown properties have credible values that will …
R.246-231-246-231-106 Preliminary determinations.
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Before the first use of any packaging for the shipment of licensed material:(1) The licensee shall ascertain that there are no cracks, pinholes, uncontrolled voids, or other defects that could significantly reduce the effectiveness of the packaging;(2) Where the maximum normal op…
R.246-231-246-231-110 Routine determinations.
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Before each shipment of licensed material, the licensee shall ensure that the package with its contents satisfies the applicable requirements of this chapter and of the license. The licensee shall determine that:(1) The package is proper for the contents to be shipped;(2) The pac…
R.246-231-246-231-120 Air transport of plutonium.
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(1) Notwithstanding the provisions of any general licenses and notwithstanding any exemptions stated directly in this chapter or included indirectly by citation of 49 C.F.R. chapter I, as may be applicable, the licensee shall assure that plutonium in any form, whether for import,…
R.246-231-246-231-130 Opening instructions.
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Before delivery of a package to a carrier for transport, the licensee shall ensure that any special instructions needed to safely open the package have been sent to, or otherwise made available to, the consignee for the consignee's use in accordance with WAC 246-221-160.[Statutor…
R.246-231-246-231-133 Public inspection of application.
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Applications for approval of a package design under this chapter, which are submitted to NRC, may be made available for public inspection, in accordance with provisions of 10 C.F.R. 2 and 9. This includes an application to amend or revise an existing package design, any associate…
R.246-231-246-231-136 Records.
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(1) Each licensee shall maintain, for a period of three years after shipment, a record of each shipment of licensed material not exempt under WAC 246-231-040(4), showing where applicable:(a) Identification of the packaging by model number and serial number;(b) Verification that t…
R.246-231-246-231-140 Advance notification of shipment of irradiated reactor fuel and nuclear waste.
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(1)(a) As specified in subsections (2), (3), and (4) of this section, each licensee shall provide advance notification to the governor of a state, or the governor's designee, of the shipment of licensed material, within or across the boundary of the state, before the transport, o…
R.246-231-246-231-150 Quality assurance requirements.
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(1) Purpose. This section describes quality assurance requirements that apply to design, purchase, fabrication, handling, shipping, storing, cleaning, assembly, inspection, testing, operation, maintenance, repair, and modification of components of packaging that are important to …
R.246-231-246-231-160 Quality assurance organization.
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(1) The licensee, certificate holder, and applicant for a certificate of compliance shall be responsible for the establishment and execution of the quality assurance program. The licensee, certificate holder, and applicant for a certificate of compliance may delegate to others, s…
R.246-231-246-231-170 Quality assurance program.
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(1) The licensee, certificate holder, and applicant for a certificate of compliance shall establish, at the earliest practicable time consistent with the schedule for accomplishing the activities, a quality assurance program that complies with the requirements of 10 C.F.R. 71.101…
R.246-231-246-231-174 Changes to quality assurance program.
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(1) Each quality assurance program approval holder shall submit, in accordance with 10 C.F.R. 71.1(a), a description of a proposed change to its NRC-approved quality assurance program that will reduce commitments in the program description as approved by the NRC. The quality assu…
R.246-231-246-231-178 Handling, storage, and shipping control.
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The licensee, certificate holder, and applicant for a certificate of compliance shall establish measures to control, in accordance with instructions, the handling, storage, shipping, cleaning, and preservation of materials and equipment to be used in packaging to prevent damage o…
R.246-231-246-231-180 Inspection, test, and operating status.
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(1) The licensee, certificate holder, and applicant for a certificate of compliance shall establish measures to indicate, by the use of markings such as stamps, tags, labels, routing cards, or other suitable means, the status of inspections and tests performed upon individual ite…
R.246-231-246-231-182 Nonconforming materials, parts, or components.
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The licensee, certificate holder, and applicant for a certificate of compliance shall establish measures to control materials, parts, or components that do not conform to the licensee's requirements to prevent their inadvertent use or installation. These measures must include, as…
R.246-231-246-231-184 Corrective action.
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The licensee, certificate holder, and applicant for a certificate of compliance shall establish measures to assure that conditions adverse to quality, such as deficiencies, deviations, defective material and equipment, and nonconformance, are promptly identified and corrected. In…
R.246-231-246-231-186 Quality assurance records.
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The licensee, certificate holder, and applicant for a certificate of compliance shall maintain sufficient written records to describe the activities affecting quality. These records must include changes to the quality assurance program as required by 10 C.F.R. 71.106, the instruc…
R.246-231-246-231-188 Audits.
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The licensee, certificate holder, and applicant for a certificate of compliance shall carry out a comprehensive system of planned and periodic audits to verify compliance with all aspects of the quality assurance program and to determine the effectiveness of the program. The audi…
R.246-231-246-231-200 Appendix A—Determination of A1 and A2.
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(1) Values of A1 and A2 for individual radionuclides, which are the basis for many activity limits elsewhere in these regulations, are given in this section, Table A-1. The curie (Ci) values specified are obtained by converting from the Terabecquerel (TBq) value. The Terabecquere…
R.246-232-246-232-001 Purpose and scope.
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(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 24…
R.246-232-246-232-004 Completeness and accuracy of information.
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(1) Information provided to the department by an applicant for a license or by a licensee or information required by statute or by the department's rules, orders, or license conditions to be maintained by the applicant or the licensee must be complete and accurate in all material…