WAC 246-221-160
Procedures for picking up, receiving, and
opening packages. (1)(a) Each licensee who expects to receive a
package containing quantities of radioactive material in excess
of the Type A1 or A2 quantities specified in WAC 246-231-200 shall
make arrangements to receive:
(i) The package when it is offered for delivery by the
carrier; or
(ii) Immediate notification from the carrier of the arrival
of the package at the carrier's terminal.
(b) Each licensee who picks up a package of radioactive
material from a carrier's terminal shall pick up the package
expeditiously upon receipt of notification from the carrier of
its arrival.
(2) Each licensee shall:
(a) Monitor for radioactive contamination the external
surfaces of any package labeled with a Radioactive White I,
Yellow II or Yellow III label unless the package contains only
radioactive material in the form of gas or in special form as
defined in WAC 246-231-010; and
(b) Monitor the radiation levels of the external surfaces of
any package labeled with a Radioactive White I, Yellow II or
Yellow III label unless the package contains quantities of
radioactive material that are less than or equal to the Type A
quantity, as defined in WAC 246-231-200; and
(c) Monitor all packages known to contain radioactive
material for radioactive contamination and radiation levels if
the package has evidence of potential contamination, such as
packages that are crushed, wet, or damaged.
(3) The monitoring shall be performed:
(a) Immediately upon receipt if there is evidence of package
degradation or any other evidence of potential contamination or
excessive radiation levels; or
(b) As soon as practicable after receipt, but no later than
three hours after the package is received at the licensee's
facility if received during the licensee's normal working hours,
or no later than three hours from the beginning of the next
working day if received after normal working hours.
(4) The licensee shall immediately notify the final delivery
carrier and, by telephone and telegram, mailgram, or facsimile,
the department when:
(a) For normal shipments, removable radioactive surface
contamination exceeds either 22 dpm/cm2 for beta-gamma emitting
radionuclides, all radionuclides with half-lives less than ten
days, natural uranium, natural thorium, uranium-235, uranium-238,
thorium-232, and thorium-228 and thorium 230 when contained in
ores or concentrates; or 2.2 dpm/cm2 for all other alpha emitting
radionuclides; or
(b) For exclusive use shipments, removable radioactive
surface contamination exceeds either 220 dpm/cm2 for beta-gamma
emitting radionuclides, all radionuclides with half-lives less
than ten days, natural uranium, natural thorium, uranium-235,
uranium-238, thorium-232, and thorium-228 and thorium 230 when
contained in ores or concentrates; or 22 dpm/cm2 for all other
alpha emitting radionuclides; or
(c) For normal or exclusive use shipments, external
radiation levels exceed two mSv/hour (200 millirem per hour) at
any point on the external surface of the package; or
(d) For exclusive use shipments where the shipment is made
in a closed transport vehicle, packages are secured in a fixed
position, and no loading or unloading occurs between the
beginning and end of transportation, external radiation levels
exceed ten mSv/hour (1000 millirem per hour) at any point on the
external surface of the package.
(5) Each licensee shall establish and maintain procedures
for safely opening packages in which radioactive material is
received, and shall assure that such procedures are followed and
that due consideration is given to instructions for the type of
package being opened and the monitoring of potentially
contaminated packaging material (including packages containing
radioactive material in gaseous form) to assure that only
background levels of radiation are present prior to disposal of
such material as nonradioactive waste.
(6) Licensees transferring special form sources to and from
a work site in vehicles owned or operated by the licensee are
exempt from the contamination monitoring requirements of
subsection (2)(a) of this section but are not exempt from the
monitoring requirement in subsection (2)(b) of this section for
measuring radiation levels to ensure that the source is still
properly lodged in its shield.
[Statutory Authority: RCW 70.98.050. 99-15-105, § 246-221-160,
filed 7/21/99, effective 8/21/99; 94-01-073, § 246-221-160, filed
12/9/93, effective 1/9/94. Statutory Authority: RCW 70.98.050
and 70.98.080. 91-15-112 (Order 184), § 246-221-160, filed
7/24/91, effective 8/24/91. Statutory Authority: RCW 43.70.040.
91-02-049 (Order 121), recodified as § 246-221-160, filed
12/27/90, effective 1/31/91. Statutory Authority: RCW 70.98.080. 87-01-031 (Order 2450), § 402-24-125, filed 12/11/86;
83-19-050 (Order 2026), § 402-24-125, filed 9/16/83. Statutory
Authority: RCW 70.98.050. 81-01-011 (Order 1570), § 402-24-125,
filed 12/8/80; Order 1095, § 402-24-125, filed 2/6/76.]