HomeMy WebLinkAboutDRC-2018-004074 - 0901a06880801d59c,..f Waste Management
4 and Radlation Control
- CLIVE SITE APR-2-7 2018- LETTER OF TRANSMITTAL
DRC- 2o18-001-0 74-
DATE: 04/26/2018
ATTN: Don Verbica — DWMRC
CC; Treesa Parker
Karen Kirkwood
RE: Transmittal 18012
Description of Documents Transmitted Qty
See attached for an update to Radiation Safety;
CL-RS-PR-115 Rev 8, Radiological Surveys
Please replace your current procedure revisions with the documents with in this
Transmittal.
You are not required to sign any documents to verify receipt of this distribution.
However, you should make every effort to ensure that your copy of the License is
current.
FROM: EnergySolutions
Document Control
Clive Facility
Authored By:
Mark White
Apr 24 2018 4:38 PM
Mark White, Radiation Safety Specialist
Oa-
Dale Thorne, Lead, Health Physics / ARSO Date
Stephen J. Long
Apr 24 2018 4:44 PM
Stephen Long, Lead, Health Physics / ARSO Date
Thomas Brown
4gter,,a.f,...i Apr 26 2018 8:16 AM
Reviewed By:
Approved By
Approved By
Date
Dale Thorne
Apr 24 2018 4:44 PM cosign
cosisn
ENERGYSOLVTIONS CL-RS-PR-115
Radiological Surveys
Revision 8
Thomas A. Brown, Radiation Safety Officer (RSO) Date
0 Non-Proprietary D New
1:1 Proprietary Title Change
Restricted Information A Revision
Safeguards Information Rewrite
Ej Sensitive Security Information Cancellation
Electronic documents, once pnnted, are uncontrolled and may become outdated.
Refer to the Intranet or the Document Control authority for the correct revision.
CL-RS-PR-115 ,
Radiological Surveys Revision 8
Table of Contents
1 PURPOSE AND SCOPE 3
1.1 Purpose 3
1.2 Scope 3
2 REFERENCES 3
3 GENERAL 4
3.1 Definitions 4
3.2 Responsibilities 7
3.3 Precautions and Limitations 7
3.4 Records 10
4 REQUIREMENTS AND GUIDANCE 1 1
5 ATTACHMENTS AND FORMS 31
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1 PURPOSE AND SCOPE
1.1 Purpose
To provide instruction for performing, evaluating and documenting
radiological conditions at the Clive Facility and to provide a consistent
method to control and prevent the spread of contamination outside the
Restricted Area while railcars and locomotives move in and out of the
Restricted Area to prepare for various aspects of waste and container
management. This procedure is also used to guide the methods used for
release of areas/materials from the Restricted Area to unrestricted status
within the EnergySolutions Controlled Area.
1.2 Scope
This procedure applies to all Radiation Safety personnel in the performance of
radiological surveys at the Clive Facility. It also applies to the collection,
preparation, analysis, and results reporting of a release survey data at
EnergySolutions Clive facility. These surveys are performed whenever
potentially contaminated areas/items need to be remediated or released from
the Clive facility's Restricted Area. This procedure does not apply to
monitoring required as part of the Environmental Monitoring Program. This
procedure scope does not include:
• Release of personnel which is covered by CL-RS-PR-120, Access
Control Points.
• Release of personal items (items carried by an entrant into the
Restricted Area that are easily accessible to survey and have a low
potential of being contaminated (e.g.. hand tools, radios, empty
drinking bottles, paperwork, and clothing carried in, but not worn in
the RA ) are released in accordance with CL-RS-PR-120, Access
Control Points.
2 REFERENCES
2.1 Clive Radiation Protection Program
2.2 EnergySolutions Radioactive Material License UT 2300249, as amended
2.3 lle (2) Material License UT2300478, as amended
2.4 U.S Nuclear Regulatory Commission HPPOS-221, Lower Limit of detection
(LLD) for Potentially Contaminated Oil, February 7, 1995
2.5 Technical Basis Document TBD07-001, Use of Ludlum Model 375-30
Radiation Monitoring System for Performing Sole Use Radiation Surveys of
Rail Cars At the Northwest Rotary Dump Facility
2.6 Multi-Agency Site Survey and Investigation Manual (MARSSIM)
2.7 U.S. Nuclear Regulatory Commission, NUREG/CR-5849, Manual for
Conducting Radiological Surveys in Support of License Termination
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2.8 CD09-0198, August 3, 2009, Letter response to the Executive Secretary's
Request for Additional Information regarding an area release
2.9 Utah Code R313-15
2.10 CL-EV-PR-014, Environmental and PCB Soil Sampling
2.11 CL-RS-PR-120, Access Control Points
2.12 CL-RS-PR-150, Posting Requirements for Radiological Hazards
2.13 Attachment II-1, State-Issued Part B Permit UTD982598898, as amended
2.14 49CFR173.403 — Contamination definition
2.15 49CFR173.443 — Contamination control
3 GENERAL
3.1 Definitions
3.1.1 49CFR173.403 Contamination Compliant Survey - Survey and release
criteria for conveyances used for the transport of Class 7 (radioactive
material) exclusive use shipments which are not considered the
package (i.e. flatbed trailers, cask trailers, intermodal railcars) and are
being shipped back with a DOT package (i.e. DOT Empty, Sole Use,
49CFR173.443(c) Compliant).
3.1.2 49CFR173.443(c) Compliant Survey - Survey and release criteria for
conveyances used for the transport of Class 7 (radioactive material)
exclusive use shipments which are considered the package (i.e.
railcars, intermodals, vans) and are remaining in exclusive use service.
3.1.3 Bates/Shipment Number — Identification number assigned by
EnergySolutions to a shipment for the purpose of tracking during the
managing of the shipment.
3.1.4 Clive Facility — All Clive Facilities, including Section 32 and
surrounding company owned properties.
3.1.5 Contact (dose rate) — A measurement of the radiation exposure rate
at the surface of the source (at a distance of approximately 1
centimeter) or any surface that the radiation penetrates.
3.1.6 Contamination — Unwanted radioactive material on the surface(s) of
structures, areas, objects, or personnel.
3.1.7 Controlled Area — The area to which access is controlled by
EnergySolutions for any purpose. Or Controlled Area — An area
owned by EnergySolutions encompassing the RA where
EnergySolutions limits access for any reason.
3.1.8 Conveyance — Any vehicle or large freight container with a capacity
of greater than 106 cubic feet for transport of radioactive material by
public highway or rail.
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3.1.9 Conveyance Survey — A survey performed on the exterior of railcars
and locomotives that will move in and out of the restricted area. The
Conveyance Survey shall consist of a radiological survey and physical
inspection to ensure no radioactive waste is present on the exterior of
locomotives and railcars.
3.1.10 Dedicated Clean Conveyance — A locomotive, gondola railcar, etc.
that is dedicated to rail lines outside of the Restricted Area. Dedicated
Clean Conveyances are presumed contamination free because:
• They are never left unattended during operation/movement
inside the Restricted Area.
• Care is taken to avoid contact with potentially contaminated
equipment and personnel.
• They are always left outside the Restricted Area during breaks
and between shifts.
• If the Clean Conveyance is used inside the Restricted Area, a
survey is performed at the end of the shift (or more often as
needed) to verify that it remains contamination free and
documented on CL-RS-PR-115-F1 Radiological Survey form.
• Survey of Clean Conveyance will include large area wipe
contamination survey and direct gamma measurement. Any
area of the conveyance that contacted any equipment, material
or personnel inside the Restricted Area will be direct frisked
for total contamination.
• If any contamination is detected in excess of the limits
specified on CL-RS-PR-115-F1 Radiological Survey form,
NOTIFY the Radiation Safety Officer immediately.
3.1.11 DOT Empty Release (EP) — Survey and release criteria for
conveyances or containers that have previously contained "Class 7"
(Radioactive) materials, that have been emptied of contents as far as
practical, and that are exempted from certain specific transportation
related regulatory requirements as detailed in 49CFR173.428.
3.1.12 General Area (dose rate)— A measurement of the radiation exposure
rate measured at a distance of geater than 30 centimeters from the
source or any surface that the radiation penetrates. General area dose
rates are normally taken at waist level.
3.1.13 Inaccessible Surface(s) — A surface on an item or piece of equipment
that cannot be directly measured (physical measurement) for the
presence of removable or fixed radioactive contamination. As
appropriate, a release survey includes an evaluation of the potential
contamination present on inaccessible surfaces.
3.1.14 Large Area Wipe (LAW) — A large area sample taken to detect
removable surface contamination. The sample medium (Masslinn'
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or equivalent) is wiped over a 300 cm2 area (approximate) using
moderate pressure.
3.1.15 Minimum Detectable Activity (MDA) - The smallest amount or
concentration of radioactive material in a sample that will yield a net
count, above system background, that will be detected with 95%
probability with only 5% probability of falsely concluding that a blank
observation represents a "real" signal. MDA depends upon the type of
instrument, the counting geometry, counting time, and the radionuclide
to be detected.
3.1.16 Non-contaminated Restricted Area (NCRA) — The area within the
Restricted Area that requires control of access and occupancy for
radiation protection purposes and is posted "Caution, Radioactive
Material" but is NOT posted as a Contamination Area or Airborne
Radioactive Material.
3.1.17 Package - The packaging together with its radioactive contents as
presented for transport.
3.1.18 Radiological Contamination — The presence of radioactive material
(RAM) in contact with an object that does not benefit from the
presence of the RAM.
3.1.19 Radiologically-Controlled Area (RCA) - Any area to which access is
controlled and that is posted because of the presence of radiation or
radioactive materials. RCAs include: Radioactive Materials Areas,
Contaminated Areas, Radiation Areas, High Radiation Areas, Very
High Radiation Areas and Airborne Radioactivity Areas.
3.1.20 Restricted Area — The area within the controlled area that requires
control of access and occupancy for radiation protection purposes.
The restricted area boundary is posted with "Caution, Radioactive
Material" and is bordered by a 6 foot high fence except in buildings
where a lockable door or other device to prevent unauthorized or
inadvertent entry is present.
3.1.21 Restricted Conveyance — A locomotive, gondola railcar, Intermodal
flat car, etc. that is located inside of the Restricted Area and is
presumed potentially contaminated. This includes incoming shipments
awaiting unloading.
3.1.22 Sole Use Release (SU) — Survey and release criteria for conveyances
that are used only for the transport of radioactive material and are
marked "For Radioactive Material Use Only."
3.1.23 Survey — An evaluation of the radiological conditions and potential
hazards incident to the production, use, transfer, release, disposal or
presence of radioactive material or other sources of radiation. When
appropriate, such an evaluation includes a physical survey of the
location of radioactive material and measurements or calculations of
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levels of radiation, concentrations, or quantities of radioactive material
present.
3.1.24 Swipe — A sample (wipe/smear) taken to detect removable surface
contamination. The sample medium is wiped over the monitored
surface in a 100 cm2 area.
3.1.25 Transport Vehicle — A cargo carrying vehicle such as an automobile,
van, tractor, truck, semi-trailer, tank car or rail car used for the
transportation of cargo by any mode.
3.1.26 Tritium Sample — A sample (swipe) taken to measure the amount of
removable surface tritium contamination per 100 cm2.
3.1.27 US. Department of Transportation (DOT) — Refers to the regulatory
agency responsible for ensuring the safe transportation of hazardous
materials.
3.1.28 Unrestricted Area — An area to which access is not controlled for the
purpose of protection of individuals from exposure to radiation and
radioactive materials and any area used for residential quarters.
3.1.29 Unrestricted Release - The removal of materials from a Radiologically
Controlled Area (RCA) to areas that do not require radiological control
of the material by the licensee.
3.1.30 Visibly Clean — Ensure that the item surfaces are sufficiently clean to
allow an appropriate radiological survey of the item. There shall be no
material that will mask or shield contamination.
3.2 Responsibilities
3.2.1 The Radiation Safety Officer (RSO) or designee is responsible for
overall radiation safety, contamination control, and compliance with
state and federal regulations and for daily oversight of the radiation
protection program in accordance with the Clive Radiation Protection
Program.
3.2.2 Lead, Health Physics / ARSO or designee, is responsible for managing
the activities of the Radiation Safety Technicians, and reporting and
managing data obtained in this procedure.
3.2.3 Radiation Safety Technicians (RSTs) are responsible for the
radiological survey of all equipment, containers and packages prior to
the release from the RA and that all activities are carried out in
accordance with all applicable procedures. They are also responsible
for performing Conveyance Surveys on rail conveyances, or for
visually observing railcars without a Conveyance Survey while outside
the restricted area.
Note: ONLY personnel qualified as RST II are authorized
to release items with inaccessible surfaces.
3.2.4 The Lead, Laboratory is responsible for:
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• Ensuring timely, accurate, and adequate on site Gamma
Spectroscopy analysis of specified soil samples;
• Ensuring samples are analyzed by Utah certified contract
laboratories;
• Ensuring minimum detectable activity (MDA) requirements are
met;
• Forwarding analytical data from gamma spectroscopy to the
RSO, Environmental Program Manager and Environmental
Monitoring Technicians;
3.2.5 The Environmental Program Manager is responsible for ensuring that
soil samples are collected and processed in accordance with approved
procedures and good practices.
3.2.6 The Environmental Monitoring Technician collects and prepares soil
samples and maintains records in accordance with CL-EV-PR-014,
Environmental and PCB Soil Sampling.
3.2.7 Area Release Coordinator is appointed by the RSO to coordinate the
release of a designated area and collects and documents all data related
to an area release.
3.2.8 The Container Management, Manager or designee is responsible for
providing Radiation Safety personnel with the type of release required
for a conveyance and/or container to be released.
3.2.9 The Shipping and Receiving Manager or designee is responsible for
ensuring that no container is delivered to a carrier unless the
requirements of this procedure are met.
3.2.10 The Rail Gate Guard is responsible for controlling rail traffic in and
out of the restricted area through the rail gates and for verifying that a
Conveyance Survey has been completed and documented on CL-RS-
PR-115-F1 Radiological Survey form, prior to any rail conveyance or
Dedicated Clean Conveyance exiting the restricted area as required by
this procedure.
Note: No pedestrian or vehicular road traffic is permitted
through Rail Gates unless authorized by RSO.
3.3 Precautions and Limitations
3.3.1 All surveys requiring work above four (4) feet shall be performed on
an approved ladder or platform that meets applicable OSHA fall
protection requirements. Personnel shall use caution when accessing,
exiting and working on transport vehicles. Three points of contact
shall be maintained while on a ladder or while accessing vehicles.
3.3.2 Radiation Safety Technicians shall be aware of any special
requirements unique to each survey.
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3.3.3 When it is necessary to perform a survey on a suspended load, utilize
extension devices to keep clear of the swing path and suspended
weight of the load.
3.3.4 Loaded trailers shall be situated on level ground and should have
wheels blocked during inspections or connected to the tractor with the
parking brake set.
3.3.5 When performing area surveys that require significant walking,
personnel should avoid treading over uneven terrain and alongside
slopes to minimize exposure to trip and fall hazards.
3.3.6 Observe contamination control practices when handling potentially
contaminated smear samples.
3.3.7 Use only calibrated and constancy checked instruments when
performing radiological surveys.
3.3.8 While wet surfaces may be surveyed for beta dose rate, RSTs shall
ensure that areas being surveyed are free of standing water per Utah
Division of Waste Management and Radiation Control (DWMRC)
Notice of Enforcement Discretion dated October 19, 2010.
3.3.9 Precautions shall be taken to prevent cross contamination of the
samples during collection and preparation. These precautions may
include, but are not limited to:
• Wear gloves as necessary during sample collection and
preparation;
• Thoroughly clean soil handling tools and equipment with water
between samples, or use disposable tools;
• Control samples to prevent possible contamination during
storage and transportation.
3.3.10 Conveyance Surveys are valid through the end of the work shift, or
until an event occurs that would require the conveyance to be
resurveyed (i.e. mud splatter, unloading event, excessive dust, etc.).
Rail Conveyances shall be visually clean prior to leaving the restricted
area.
3.3.11 Conveyance Surveys are required for Dedicated Clean Conveyances
before the end of the shift in which they enter the Restricted Area. .
The Rail Gate Guard shall ensure a Conveyance Survey has been
appropriately completed for all Conveyances, or that an RST will
observe their movement outside the Restricted Area.
3.3.12 Dedicated Clean Conveyances shall not leave the Controlled Area
without being in direct control of EnergySolutions personal. If the
Dedicated Clean Conveyance is to remain out of the Controlled Area
for more than 12 hours a documented release survey is required.
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3.3.13 Railcars and Locomotives approved for Conveyance shall not be left
unattended while outside the Restricted Area.
3.3.14 Dedicated Clean Conveyances shall not be left unattended while inside
the Restricted Area.
3.3.15 Personnel performing Conveyance Surveys or involved in rail
movement shall receive training in Safe Rail Operations.
3.4 Document and Control Records
3.4.1 Electronic versions of CL-RS-PR-115-F1, Radiological Survey Form,
are acceptable for use in accordance with this procedure, PROVIDED
that the form includes all minimum required information.
3.4.1.1 DOCUMENT survey measurements as soon as practical
following the completion of the measurement on the
radiological survey form.
3.4.1.2 The completed radiological survey form shall include the
following information at a minimum:
• Technician performing the survey
• Date and location of the survey
• Model(s), serial number(s), and calibration due
date of survey instrument(s) used
• Instrument background and MDA data.
• Reason for survey
• Area postings, boundaries and verification
readings as applicable
• Review signature and date reviewed
3.4.1.3 NUMBER surveys with multiple pages for accountability (i.e.
1 of 2, 2 of 2).
3.4.1.4 MAKE all entries in black or blue ink.
3.4.1.5 ENSURE all documentation is complete and legible.
3.4.1.6 IF acronyms are used, THEN PROVIDE a legend on the
survey form to explain their meaning.
3.4.2 CL-RS-PR-115-F3, Restricted Area Release Soil Data Form — The
area release coordinator shall ensure that the CL-RS-PR-115-F3,
Restricted Area Release Soil Data form is completed for each area
surveyed. This form shall be included with the area release CL-RS-
PR-115-F1 Radiological Survey form.
3.4.2.1 CL-RS-PR-115-F1, Radiological Survey Form - shall be
completed to document all details of the area release. Attach
all supporting documents such as maps and CL-RS-PR-115-F3,
Restricted Area Release Soil Data forms.
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3.4.2.2 The RSO shall provide a report to the DWMRC including the
details and sample results of all areas released from the
Restricted Area. The report will also capture commitments
made in reference 2.10, including:
• A history and narrative associated with the
release area;
• Justification for the sampling method and
frequency used;
• A discussion of remediation activities associated
with the release;
• Rough estimates of volumes removed during
remediation efforts;
• Procedures used in the release;
• Reported numbers for all radionuclides that
exceed action limits;
• All gamma spec reports applicable to the
release; and,
• QA/QC sampling results.
3.4.3 The Radiation Safety Officer (RSO) shall TAKE appropriate follow-
up actions to ensure that exposures to personnel are ALARA based on
radiological survey results.
3.4.4 The completed radiological survey forms should be transmitted to
Document Control within 60 days of review.
4 REQUIREMENTS AND GUIDANCE
4.1 Radiological Surveys
4.1.1 Routine Surveys
4.1.1.1 Routine surveys are not intended to provide exhaustive
characterizations of each area surveyed. Data should, however
present a "snapshot" of radiological conditions as they exist at
the time of the survey.
4.1.1.2 Routine dose rate surveys are usually general area
measurements taken at approximately waist height. Unusual
reading locations and contact readings are annotated as such on
the radiological survey form.
4.1.1.3 Gamma dose rate surveys at the Restricted Area perimeter,
office and lunch areas are intended to assess potential dose to
unmonitored members of the public (non-radiation workers).
Note: All surveys measuring dose to an
unmonitored member of the public
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must be capable of distinguishing less
than 50 mierorem per hour.
4.1.1.4 Restricted-area surveys are to be performed with instruments
capable of verifying Restricted Area posting requirements.
Note: Action Level = 50 microrem per hour
4.1.1.5 Gamma dose rate surveys inside the Restricted Area are
intended to assess work area conditions on a regular basis.
Area dose rate conditions are documented to verify compliance
with postings, Radiation Work Permit (RWP) requirements,
and ALARA considerations for radiation workers.
Note: Action Level = Area Postings
4.1.1.6 The location of RADIATION AREA and HIGH RADIATION
AREA boundaries shall be annotated on the survey form.
4.1.1.7 All RADIATION AREA and HIGH RADIATION AREA
boundaries shall be verified adequate and the maximum dose
rate at each boundary indicated on the survey form.
4.1.1.8 All routine surveys performed for contamination purposes shall
include the use of swipes.
4.1.1.9 Unusual readings shall be investigated by the Radiation Safety
Officer. Corrective actions for out-of-compliance conditions
shall be completed as soon as possible.
4.1.2 Weekly Routine Surveys
Note: EnergySolutions Radioactive Material License UT
2300249 Condition 22 stipulates that certain Weekly
Routine Surveys shall be performed on a monthly
basis when not in operation / use. Surveys listed in
this section (4.1.2) shall be performed on a weekly
basis unless approval is given by the Radiation
Safety Officer. The operafional status of the
specified areas shall be documented weekly.
4.1.2.1 Contamination smear surveys shall be performed WEEKLY in
the following areas, at a MINIMUM:
• Eating Areas
• Change Areas
• Office Areas
• Decontamination Facilities
• Access Control Points including Personnel
Monitors
• Mixed Waste Facility
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• Shredder Facility and Control room
• Rotary Dump Facility and Control room
• The exhaust port (or area) of any vacuum
cleaner used inside the Restricted Area shall be
surveyed for removable contamination by a disc
smear counted on the 3030 or equal. Results of
this survey shall be documented on the survey
form. Any results greater than or equal to 100
dpm/100 cm2 alpha or 1,000 dpm/100 cm2 beta-
gamma shall be reported to the ARSO.
4.1.2.2 Dose Rate surveys shall be performed WEEKLY in the
following areas, at a MINIMUM:
• Perimeter of Restricted Area
• Office Areas
• Eating Areas
• Change Areas
• Decontamination Facilities
• Mixed Waste Facility
• Perimeter of posted High Radiation area(s)
4.1.2.3 The Radiation Safety Officer shall designate selected areas to
be monitored WEEKLY for surface tritium contamination.
Note: Surface tritium measurements are
made by wiping a paper filter (swipe)
over a 100 cm2 area. De-ionized water
is applied to either the monitored
surface or the filter paper before
wiping to improve the tritium
collection efficiency. Tritium swipe
samples are placed in scintillation
vials (glass or plastic) and counted
using the Liquid Scintillation Counter.
Note: Tritium samples that are collected for
Routine Surveys should be counted as
soon as possible after collection
(usually within two to three days— not
to exceed seven days).
4.1.2.4 A Weekly Routines Cover Sheet shall be attached to the
Weekly Routines Survey Package and reviewed by the
Radiation Safety Officer.
4.1.3 Quarterly Routine Surveys
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4.1.3.1 A radiological survey of the rail line located OUTSIDE the
Restricted Area shall be performed QUARTERLY, in
accordance with the LLRW Surety requirements.
Note: Prior to initiating each quarterly rail
survey, all railcars and other obstacles
are removed from the line of rail
being inspected. After clearing, a
comprehensive walkover survey is
conducted on all accessible surfaces of
the rail and ballast using a Ludlum
model 193 or 193-6 or similar
instrument (per Section 4.3.2.3).
4.1.3.2 A Radiological survey of the Administration Bldg shall include
Gamma exposure rates as well as contamination smears.
4.1.4 Job-Related Surveys
Provide information on job-related surveys to adequately identify the
magnitude and extent of radiological hazards in the work area. This
information may include but is not limited to:
• Potential hot spots on containers, systems or components.
• Container or equipment breaches or leaks.
• Changes in dose rates caused by waste disposal operations.
• Access and egress routes where dose rates are significant.
• Any changes in conditions, which require follow-up action,
intervention, or Radiation Safety Supervision notification to
control the spread of contamination or minimize personnel
exposure.
• Area postings/boundaries as applicable.
4.1.5 Special Surveys
Provide information on special surveys to identify possible
radiological hazards following a unique incident or evolution and to
comply with procedural requirements.
4.1.6 Dose Rate Measurements
4.1.6.1 General Area Dose Rate
4.1.6.1.1 OBTAIN general area radiation surveys at
greater than a distance of 30 centimeters (1 foot)
from the source where possible (e.g. waist
level).
Note: Additional measurements may be needed
anywhere up to six feet above surfaces
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occupied by workers in non-uniform
radiation fields.
4.1.6.2 Contact Dose Rate
4.1.6.2.1
4.1.7 Beta Dose Rate
OBTAIN a contact dose rate at the surface of
the source (at a distance of approximately 1
centimeter) or any surface that the radiation
penetrates.
4.1.7.1 OBTAIN a Beta Dose Rate for work on components when beta
survey is required.
Note: The Beta Dose Rate is obtained with
an ion chamber type instrument by
the following:
OW-CW X BCF = Beta Dose Rate
(mrad/hr or rad/hr).
Where: OW = Open Window reading
CW = Closed Window reading
BCF = Beta Correction Factor found on
meter calibration label
4.1.8 Recording Dose Rate Measurements
4.1.8.1 UNDERLINE general area dose rate measurements at greater
than 30 centimeters. Example:
5
4.1.8.2 RECORD contact dose rate measurements enclosed in a box.
Example:
5
4.1.8.3 RECORD 30-centimeter dose rates in a box directly below the
contact dose rate. Example:
5
1
4.1.8.4 In addition to the above, narrative descriptions are acceptable
provided that the radiological conditions are adequately
described.
Example: General area dose rates <0.2mR/hr
4.1.8.5 RECORD dose rate measurements according to the
instrument's applicable units. (i.e. urem/hr for a Bicron and
mR/hr for a R020, etc.).
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RECORD dose rate measurements for other than y
(gamma) radiation, followed by the appropriate symbol:
f3 for beta,
q for neutron.
4.1.9 Swipe Surveys
4.1.9.1 OBTAIN a sufficient number of swipes to ensure the area is
adequately represented by the survey.
4.1.9.2 PERFORM a swipe survey by wiping an area of about 100
cm2 (or the entire surface of smaller items) using moderate
pressure.
4.1.9.3 SURVEY areas adjacent to contaminated areas to verify
adequate contamination controls.
4.1.9.4 SURVEY components and equipment in the immediate
vicinity of work areas to verify the effectiveness of
contamination controls.
4.1.9.5 MEASURE each swipe using an appropriate instrument in
accordance with applicable procedures.
Note: The background should be low
enough to detect activity consistent
with the anticipated radiological
conditions (in accordance with the
applicable instrument operating
procedure).
Note: Typically, counting instrumentation
should have MDA values less than or
equal to 75% of the level of interest.
4.1.9.6 RECORD swipe results in dpm/100cm2.
4.1.9.7 INDICATE swipe locations with a NUMBER and CIRCLE.
Example:
4.1.10 Large Area Wipe (LAW) Surveys
4.1.10.1 PERFORM a Large Area Wipe (MasslinnTm or
equivalent) survey by wiping an area of approximately
300cm2 using moderate pressure.
4.1.10.2 MEASURE the Large Area Wipe using an appropriate
instrument in accordance with applicable procedures.
4.1.10.3 DIVIDE the total contamination reading by three (3).
4.1.10.4 RECORD LAW results in units of dpm/100 cm2.
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4.1.10.5 INDICATE LAW results with a NUMBER and
CIRCLE with ARROWS that show the area
represented by the survey.
Example:
4.1.11 Direct Frisk survey
4.1.11.1 PERFORM direct frisk surveys in accordance with the
procedure for the instrument used.
4.1.11.2 PERFORM frisk scan surveys at no more than 1-2"
per second.
4.1.11.3 PERFORM integrated measurement at all location
where an audible potential for contamination is
detected.
4.1.11.4 INDICATE integrated measurements with a
NUMBER in a TRIANGLE.
Example:
4.1.11.5 RECORD results in units of dpm/100 cm2.
4.1.11.6 RECORD measurement results that are less than the
Minimum Detectable Activity (MDA) as "<MDA,"
OTHERWISE, RECORD the actual number for the
measurement on the radiological survey form.
4.1.11.7 RECORD the applicable instrument background count
on the radiological survey form.
4.1.11.8 RECORD the applicable instrument Minimum
Detectable Activity (MDA) on the radiological survey
form.
4.1.12 Notifications
NOTIFY the Radiation Safety Officer of any condition(s) in which
radiation and/or contamination levels are found to be above RWP
requirements, exceed acceptable posting limits, or where levels are
found to be higher than expected as follows.
4.1.12.1 Gamma dose rates that exceed 50 microrem per hour at
the RESTRICTED AREA boundary.
4.1.12.2 Gamma dose rates above 4000 microrem (4 millirem)
per hour at 30 cm from any surface outside a posted
RADIATION AREA.
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4.1.12.3
4.1.12.4
4.1.12.5
4.1.12.6
Gamma dose rates above 80,000 microrem (80
millirem) per hour at 30cm from any surface outside a
posted HIGH RADIATION AREA.
Removable contamination level greater than the
following outside a posted CONTAMINATION
AREA:
20 dpm/100cm2 alpha or
200 dpm/100cm2 beta
Removable contamination levels greater than the
following outside a posted High Contamination Area
500 dpm/100cm2 alpha or
50,000 dpm/100cm2 beta
Containerized Waste Facility (CWF)
The following notifications for the CWF are in addition
to the requirements listed above:
• Any cask found to be above 50,000
dpm100cm2 (removable internal
contamination) will require notification of the
generator (in addition to the Radiation Safety
Officer) to determine further actions prior to
return shipment of the cask (i.e. decon).
4.1.12.7 VTD Condensate Totes
An extensive gamma survey of all VTD condensate
totes, and the tractor and trailer they are carried in shall
be performed prior to shipment. The RSO shall be
notified if contact dose rates on the totes exceed 15
µR/hr or if elevated dose rates on the tractor or trailer
are detected.
4.2 Restricted Area Material Release Survey
4.2.1 General Requirements
4.2.1.1 All personnel surveying, and releasing equipment, conveyances
and containers from the restricted area shall be qualified as an
RST and be trained on this procedure
4.2.1.2 Prior to performing a release survey, an item inspection shall
be done to identify any potential safety hazards. If a safety
hazard is found, contact supervision prior to continuing work
activities.
4.2.1.3 The shipment number will be used on the survey
documentation to identify the release survey and will apply to
both the transport vehicle and conveyance (as applicable).
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4.2.1.4 Prior to release of the transport vehicle or conveyance, ensure
that the previously required labeling, markings, and placards
are either removed or unrecognizable.
4.2.1.5 Surfaces of tools and equipment which are likely to be
contaminated, but are of such size, construction, or location as
to make the surfaces inaccessible for measurement, shall be
presumed to be contaminated unless a process evaluation or
indirect survey can support a release of the equipment without
surveying inaccessible areas.
4.2.1.6 All transport vehicles and conveyances shall be externally
visibly clean prior to leaving the RA.
4.2.1.7 Portions of equipment that are used in the RA to move released
items should have the parts that contact the released items
surveyed for removable contamination prior to managing the
items to help prevent recontamination of the item.
4.2.1.8 When RA equipment is used for the unloading of
conveyances/containers, only surfaces that will break the clean
area boundary need to be surveyed for removable
contamination to help prevent the spread of contamination to
clean areas
4.2.1.9 The default release limits specified in this procedure are based
on the most restrictive limits for the isotopes potentially
present at the Clive Facility.
4.2.1.10 IF the nuclides present on a surface are known OR the
presence of certain nuclides on the surface can be excluded
through process or waste stream knowledge or nuclide specific
analytical results, THEN OBTAIN the Radiation Safety
Officer authorization to use the appropriate release criteria in
Radioactive Material License UT 2300249 Condition 27;
4.2.2 Release Type and Instruments
4.2.2.1 The Container Management, Manager shall ESTABLISH the
type of release survey required.
4.2.2.2 The RST shall SELECT and PREPARE appropriate survey
instruments in accordance with the applicable instrument
procedure(s).
4.2.2.3 ENSURE that instruments used are appropriate for the
potential contamination/nuclides that are present.
4.2.3 DOT Empty Package Release Survey
4.2.3.1 ENSURE the package is emptied as far as practical of
radioactive materials.
4.2.3.2 SURVEY the item for radiation and contamination.
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4.2.3.3 ENSURE the following:
• Internal loose surface contamination levels are
less than 240,000 dpm/100 cm2 beta-gamma and
24,000 dpm/100 cm2 alpha, averaged over 300 2. CM ,
• External loose surface contamination levels are
less than 2,400 dpm/100 cm2 beta-gamma and
240 dpm/100 cm2 alpha, averaged over 300 cm2;
• External container radiation levels at all points
are less than 0.5 mrem/hr at contact.
4.2.3.4 COVER or REMOVE any previously used labels and
markings.
4.2.3.5 APPLY an "Empty" label.
4.2.3.6 MARK the outside of each package with the four digit UN
identification number preceded by the letters UN.
4.2.3.7 DOCUMENT survey results on CL-RS-PR-115-F1,
Radiological Survey Form.
4.2.4 Sole Use Release Survey
4.2.4.1 ENSURE the container is emptied as far as practical of
radioactive materials.
Note: For Sole Use containers, there must be
less waste material than consignment
activities given in 49CFR173.436.
4.2.4.2 COVER or REMOVE any previously used labels, placards or
markings.
4.2.4.3 SURVEY the item for radiation and contamination.
4.2.4.4 ENSURE the following:
• External loose surface contamination levels are
less than 2,400 dpm/100 cm2 beta-gamma and
240 dpm/100 cm2 alpha, averaged over 300 cm2;
• Internal dose rate at any point does not exceed
10.0 mrem/hr at the surfaces or less than 2.0
mrem/hr at 1 meter from the surface.
Note:
Note:
Sole Use dose rate surveys may be
performed with Ludlum Model 375-30
Rotary Monitor.
Internal dose rate limits may be
verified by surveying the external
surfaces of the conveyance/container
as detailed in Reference 2.8.
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• IF the maximum manual survey
results are less than 1,000 µR/hr (1.0
mR/hr) at 30 cm from all external
surfaces, the car can be released as
Sole Use.
4.2.4.5 ENSURE each package is stenciled with the words "For
Radioactive Material Use Only" in letters at least 3 inches
high in a conspicuous place on both sides of the exterior of the
packaging.
4.2.4.6 DOCUMENT survey results on CL-RS-PR-115-F1,
Radiological Survey Form.
4.2.5 Performance of 49CFR173 403 and 443(c) Compliant Surveys
49CFR173 403 and 443(c) Compliant Surveys (hereafter referred to
403 and 443(c)) are very similar with only the following differences:
• 403 surveys require total contamination surveys (i.e. fixed and
removable) but do not require dose rate surveys
• 443(c) surveys require removable contamination and dose rate
surveys
4.2.5.1 DETERMINE that the item meets the defmition of a transport
vehicle, conveyance, or package.
4.2.5.2 ENSURE that item surfaces are sufficiently clean as to allow a 1 radiological survey of the item.
4.2.5.3 SURVEY the item for radiation and contamination.
4.2.5.3.1 IF the item has inaccessible surfaces, THEN:
4.2.5.3.1.1 PERFORM representative
measurements AND/OR;
4.2.5.3.1.2 PERFORM an evaluation of the
potential for contamination of
inaccessible surfaces through a
review of process/use history
AND/OR;
4.2.5.3.1.3 DISMANTLE/DISASSEMBLE
the item as needed to gain access
to the surfaces;
Note: ONLY personnel
qualified as RST II are
authorized to release
items with inaccessible
surfaces.
Note: The 403/443(c) Survey
Criteria are as follows:
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• Survey results indicate
that internal and
external fixed (403) and
removable (403 &
443(c)) contamination
are less than 240
dpm/100 crn2 alpha and
2400 dpm/100 cm2 beta.;
• (443(c) only) survey
results indicate that
internal and external
contact radiation dose
rates are less than
0.5mrem/hr.
4.2.5.4 DOCUMENT survey results on CL-RS-PR-115-F1,
Radiological Survey Form.
4.2.5.5 COMPARE survey results to the criteria listed above.
• IF survey results are less than the criteria,
THEN the item may be released from the RA.
OTHERWISE, do not release the item from the
RA as 403 or 443(c) Compliant.
4.2.5.6 MOVE individual containers that are 403 or 443(c) Compliant
into a designated container storage area.
Note: This does not apply to railcars or
containers loaded on rail cars.
4.2.6 443(c) Compliant Container Storage Survey Requirements
Note: For the purpose of this procedure, Shipping and
Receiving personnel are designated as Container
Return Inspectors and are authorized to sign
Container Return Inspecfion Checklist.
Note: The container storage areas are Radioactive
Material areas and shall be treated as such in
accordance with in accordance with CL-RS-PR-150,
Posting Requirements for Radiological Hazards.
4.2.6.1 443(c) compliant containers stored in a container storage area
for NOT MORE than (30) thirty days may be shipped from
the site based on the initial survey.
4.2.6.2 443(c) compliant containers stored in a container storage area
for MORE than (30) thirty days shall have a new 443(c)
survey performed.
Note: To account for the fact that some dirt or mud from
the Non-Contaminated Radioactive Material Area
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may be present on external surfaces of these
containers, the release survey may contain a
clarification in the Remarks section such as:
"External surfaces verified to contain no visible
radiological waste material."
4.2.6.2.1 DOCUMENT a complete 443(c) survey.
4.2.6.2.2 NOTIFY the RSO of any container that fails to
meet the radiological, physical, or visibly clean
requirements.
4.2.6.2.3 When the survey is complete and documented,
INSTALL a new security seal.
4.2.6.2.4 NOTE the new seal number in the Container ID
space of the survey form.
4.2.6.2.5 COMPLETE Container Return Inspection
Checklist
4.2.7 Performance of Unrestricted Release Surveys
4.2.7.1 USE waste stream knowledge (manifests, waste stream
profiles, etc.), process knowledge (handling of the
item/equipment on site), and/or nuclide specific analytical
results to evaluate the potential nuclides presence on the
surface(s) of the item.
4.2.7.2 ENSURE that item surfaces are sufficiently clean to allow an
appropriate radiological survey of the item.
• IF both alpha- and beta-gamma emitting
nuclides are potentially present, THEN the
limits for alpha- and beta-gamma emitting
nuclides apply independently;
• IF any alpha nuclides potentially present on the
surface of the item are unknown, AND any beta
nuclides potentially present on the surface of the
item are unknown, THEN the appropriate
unrestricted release criteria are as follows:
Contamination
Type
Total By Direct
Measurement
(dpm/100cm2)
Removable
(dpn1/100cm2)
Alpha 100 20
Beta 1,000 200
Note: The unknown alpha contamination
unrestricted release criteria are based
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on transuranics. The unknown beta
contamination unrestricted release
criteria are based on Sr-90.
• IF the nuclides potentially present on a surface
are known OR the potential presence of certain
nuclides on the surface can be excluded through
process or waste stream knowledge OR nuclide
specific analytical results are available for the
item, THEN OBTAIN the Radiation Safety
Officer authorization to use the appropriate
unrestricted release criteria listed in Table 4.6
below;
• IF the direct measurement contamination level
exceeds the above limits in any localized area of
not more than 100 cm2 BUT do not exceed 3
times the above limits THEN OBTAIN the
Radiation Safety Officer authorization to use the
appropriate unrestricted release criteria listed in
Table 4.6 below:
TABLE 4.6
NUCLIDES AVERAGE b c MAXIMUM b d REMOVABLE b e f
U-Nat, U-235, and
associated decay products
5,000
dpm/100cm2
15,000 dpm/100
cm2
1,000 dpm/100
cm2
Transuranics, Ra-226, Ra-
228, Th-230, Th-228,
Pa-231, Ac-227, 1-125,
1-129
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, 1-131, 1-133
1,000 dpm/100
cm2 3,000 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
5,000 dpm/100 cm2
15,000 dpm/100
cm2 1,000 dpm/100
Crn2
Notes:
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
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appropriated detector for background, efficiency, and geometric factors associated with
the instrumentation.
• 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
obj ect.
The maximum contamination level applies to an area of not more than 100 cm2.
• 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.
• The average and maximum radiation levels associated with surface contamination resulting
from beta-gamma emitters shall 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.
4.2.7.3 SURVEY the item for radiation and contamination.
4.2.7.3.1 IF the item has inaccessible surfaces, THEN:
4.2.7.3.1.1 PERFORM representative
measurements AND/OR;
4.2.7.3.1.2 PERFORM an evaluation of the
potential for contamination of
inaccessible surfaces through
consultation with a qualified
subject matter expert (SME) as
needed and a review of
process/use history AND/OR;
4.2.7.3.1.3 DISMANTLE/DISASSEMBLE
the item as needed to gain access
to the surfaces.
Note: ONLY personnel
qualified as RST II are
authorized to release
items with inaccessible
surfaces.
Note: The SME must be
present during the
survey when releasing
heavy equipment or
other complex items.
Note: The Unrestricted
Release Criteria are as
follows:
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• Survey results indicate
that removable alpha
and beta contamination
on all surfaces of the
item (accessible and
inaccessible) are less
than the applicable
"Removable (dpm/100
cm2)" limit in Table 4.6;
• Survey results indicate
that direct alpha and
beta measurement
results on all surfaces of
the item are less than
the applicable "Total by
Direct Measurement
(dpm/100 cm2)" limit in
Table 4.6.
Note: The Clive site does not
have license authority to
release potentially
volumetrically-
contaminated materials.
Contact the RSO for
guidance on license
authorization and for
MDA requirements
when determining if
fluid is radioactively-
contaminated. (See U.S
Nuclear Regulatory
Commission HPPOS-
221, Lower Limit of
detection (LLD) for
Potentially
Contaminated Oil,
February 7, 1995,
Reference 2.4).
4.2.7.4 DOCUMENT survey results on CL-RS-PR-115-F1,
Radiological Survey Form.
4.2.7.5 COMPARE survey results to the applicable unrestricted
release limits.
• IF survey results are less than the applicable
unrestricted release limits, THEN the item may
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be released from the RA. OTHERWISE,
CONTINUE;
• IF actual direct measurements are greater than
the total by direct measurement unrestricted
release criteria, AND less than three (3) times
the total by direct measurement unrestricted
release criteria, THEN CONTACT the
Radiation Safety Officer for guidance regarding
release of the item.
4.2.8 DOT Empty Survey Requirements for Release from the container
storage area
Note: The container storage areas are Radioactive
Material areas and shall be treated as such in
accordance with in accordance with CL-RS-PR-150,
Posting Requirements for Radiological Hazards.
4.2.8.1 DOT Empty containers stored in a container storage area for
NOT MORE than (30) thirty days may be released from the
site based on the survey done at the time of release.
4.2.8.2 For DOT Empty containers stored in a container storage area
for MORE than (30) thirty days, shall have a new
EXTERNAL survey performed.
Note: To account for the fact that some dirt
or mud from the Non-Contaminated
Radioactive Material Area may be
present on external surfaces of these
containers, the release survey may
contain a clarification in the Remarks
section such as:
"External surfaces verified to contain
no visible radiological waste
material." 1
4.2.8.2.1 DOCUMENT a DOT Empty EXTERNAL
survey.
4.2.8.2.2 NOTIFY the RSO of any container that fails to
meet the radiological, physical, or visibly clean
requirements.
4.2.8.2.3 COMPLETE Container Return Inspection
Checklist.
4.3 Restricted Area Release Survey
4.3.1 General Compliance
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4.3.1.1 All area release plans, maps, results and details will be
approved by the RSO.
4.3.1.2 A Chain of Custody (COC) Form or equivalent shall
accompany all soil transferred between Departments or offsite
for analysis.
4.3.1.3 Access to all survey areas from the unrestricted area shall be
controlled in accordance with CL-RS-PR-120, Access Control
Point Procedure.
4.3.1.4 To prevent recontamination of areas sampled and/or
remediated, access to the survey area from the remainder of the
Restricted Area shall be controlled.
4.3.1.5 All area postings in place pursuant to CL-RS-PR-150, Posting
Requirements for Radiological Hazards, shall remain in place
until the RSO has approved release of the area.
4.3.1.6 In accordance with the sampling frequency associated with
Table 1 of the Environmental Monitoring Plan, one split
sample and one duplicate sample will be obtained for every 15
samples obtained during a release.
4.3.1.7 All split sampling pairs will be analyzed on EnergySolutions
internal gamma spectroscopy instrument for quality assurance
purposes.
4.3.1.8 One set of duplicates will be analyzed on EnergySolutions
internal gamma spectroscopy instrument. The opposing set of
duplicates will be sent to an offsite laboratory and compared
against EnergySolutions' results.
Note: In the event a sample release does not
exceed 15 samples, a minimum of two
splits and two duplicate samples will
be obtained per release.
4.3.2 Area Characterization
4.3.2.1 DELINEATE the boundary of the area to be released by rope,
paint markings or other method sufficient to identify the area.
4.3.2.2 GENERATE a map of the area.
4.3.2.3 PERFORM a walkover scan of all accessible portions of the
area using a Ludlum Model 193 or 193-6 or similar survey
instrument.
4.3.2.4 MARK any points where the scan survey detects activity of 2
sigma above background or greater as indicated by the
instrument low alarm.
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4.3.2.5 PERFORM a visual inspection of survey area looking for any
visual indication of potential for contamination, IF any visual
indications are noted, then continue with step 4.3.2.6.
Note: Pay particular attention to vehicle or
pedestrian traffic areas, low lying
areas, discolored areas or any other
area that might indicate a higher
potential for soil contamination as
well as all locations identified in step
4.3.2.4 above.
4.3.2.6 PERFORM direct frisk readings using the Model 2360 with
Model 43-93 Probe in any areas that were noted to have
indication of potential for contamination in step 4.3.2.5 above.
4.3.2.7 PERFORM integrated readings with the 43-93 or similar
instrument in any area where an audible alpha was detected or
any increase in beta background was noted in step 4.3.2.6.
4.3.2.8 MARK any points where the scan survey detects activity at or
above the following limits:
• 100 dpm/100 cm2 alpha or
• 1,000 dpm/100 cm2 beta.
4.3.2.9 NOTIFY the RSO of any area that exceeds the guidelines in
4.3.2.8.
4.3.3 Area Soil Sampling
4.3.3.1 COLLECT soil samples from any areas identified as
potentially having elevated activity levels in sections 4.3.2
above. An additional single randomly selected RCRA soil
sample shall be collected for targeted release areas associated
with the management of wastes governed by the State-Issued
Part B Permit (UTD982598898) and analyzed for the
parameters required for incoming shipment off-site analyses as
dictated by Reference 2.15.
4.3.3.2 PERFORM a direct µR/hr contact reading at the location of all
soil samples before the sample is taken and RECORD all
results on the CL-RS-PR-115-F3, Restricted Area Release Soil
Data form.
4.3.3.3 Area release soil sample locations, frequency, and analyses
shall meet the requirements established by the RSO.
4.3.3.4 References 2.8 and 2.9 should be used as aides in selection of
the minimum number and locations of samples obtained.
4.3.3.5 Soil samples shall be collected at locations approved by the
RSO.
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Note: A minimum of 500 grams of soil will
be collected from each designated
sample point.
4.3.3.6 The Environmental Monitoring Technician or designee shall
NOTIFY the RSO and Environmental Program Manager when
soil sample analysis results are available
4.3.3.7 Area release soil samples shall not exceed the following limits:
• 5 pCilg for any natural radionuclide except K-
40;
• 3 pCi/g for Cs-137;
• 2 pCi/g for any other man-made radionuclide;
• Limits included in Reference 2.15 (when the
single RCRA soil sample is required to be
obtained, as noted in section 4.3.3.1).
4.3.3.8 If soil samples exceed the limits listed in section 4.3.2.7, then
remediation activities will proceed under the direction of the
RSO, and resampling instituted.
4.4 Conveyances
4.4.1 Restricted Conveyances
4.4.1.1 Radiation Safety personnel shall perform a survey on
Conveyances that are required to temporarily leave the
Restricted Area or be available to continuously observe
Conveyances while they are outside the restricted area.
4.4.2 The RST shall document the survey results on CL-RS-PR-115-F1
Radiological Survey form.
4.4.3 Dedicated Clean Conveyances
4.4.3.1 Rail Gate Guards shall inform the RST of the entry of
Dedicated Clean Conveyances into the Restricted Area and
request a conveyance survey be performed before the end of
the shift.
4.4.3.2 Dedicated Clean Conveyances can enter and exit the Restricted
Area throughout the shift to facilitate railcar movements as
required for operational support.
4.4.3.3 Locomotive Operators and Switchman/Brakeman shall
accompany Dedicated Clean Conveyances at all times while
inside the Restricted Area.
Note: Newly arrived rail shipments can be
moved in and out of the Restricted
Area without a conveyance survey as
required to position the cars for
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rolling according to priorities
established by management, provided
that they are always accompanied by
an RST.
4.4.3.4 Radiation Safety personnel shall perform a survey on
Dedicated Clean Conveyances.
4.4.3.5 The RST shall document the survey results on CL-RS-PR-115-
F1 Radiological Survey form.
4.4.3.6 The Rail Gate Guard shall ensure the conveyance survey is
performed on Dedicated Clean Conveyances prior to exiting
the Restricted Area before the end of the shift.
4.5 Railcar Release Log
4.5.1 A Railcar Release Log shall be created for all railcars being released
from the Restricted Area.
Note: This requirement does not apply to Conveyances
that are temporarily leaving the Restricted Area and
have been surveyed in accordance with section 4.4.
4.5.2 Railcars included in this log shall have their exterior surfaces surveyed
for removable contamination and for dose. Contamination and dose
levels on the exterior surfaces shall meet the criteria for which they
were previously surveyed (i.e. — DOT Empty, Sole Use, etc.).
Note: LAWs provide a sufficient measure of removable
contamination for this survey.
4.5.3 Railcar Release Log and associated external surface survey shall be
documented on CL-RS-PR-115-F1, Radiological Survey form.
5 ATTACHMENTS AND FORMS
5.1 CL-RS-PR-115-F1, Radiological Survey Form, Example
5.2 CL-RS-PR-115-F2, Weekly Routines Cover Sheet, Example
5.3 CL-RS-PR-115-F3, Restricted Area Release Soil Data Form, Example
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1
1
2
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Attachment 5.1 — CL-RS-PR-115-F1, Radiological Survey Form (Example)
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Rita Alpha Beta Alpha
EN MGM/XMAS
Weekly Routines Cover Sheet
CL-RS-PR- 115-P2
Rev 0
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CL-RS-PR-115
Radiological Surveys Revision 8
Attachment 5.2 — CL-RS-PR-115-F2, Weekly Routines Cover Sheet (Example)
Non-Proprietary Page 33 of 35
CL-RSPR-l15-F3
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CL-RS-PR-115
Radiological Surveys Revision 8
DOCUMENT SUMMARY FORM
Please provide the following information for new/revised documents.
Forward the completed form, review comment forms, approved document,
and electronic file, to Document Control.
Document No.: CL-RS-PR-115 Revision No.: 8
Title: Radiological Surveys
Special Status (i.e. Restricted; SSI; etc.): NA
If special status is applicable, please note any special distribution/handling requirements:
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Summary of changes (if this is a revision):
- Changed "Visibly Clean" definition to read, "Ensure that the item surfaces are sufficiently clean to allow an
appropriate radiological survey of the item. There shall be no material that will mask or shield
contamination."
- Deleted part of the note in 4.2.4.1 related to quantifying the amount of waste material based on visibly
clean.
- Deleted 4.2.5.2 statement about being visibly clean of standing debris.
El Yes T No
0 Yes 5T No
This document requires evaluation per the requirements of a license. If yes, attach evaluation
results.
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Type of revision: X Contains technical changes r7 Contains only administrative changes
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Non-Proprietary Page 35 of 35