Radia tion Protec tion Pllan...October 2013 1.0 PURPOSE AND SCOPE This Radiation Protection Plan...
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Transcript of Radia tion Protec tion Pllan...October 2013 1.0 PURPOSE AND SCOPE This Radiation Protection Plan...
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Table of Contents
1.0 PURPOSE AND SCOPE ................................................................................................................. 1
2.0 APPLICABILITY ............................................................................................................................ 1
3.0 GENERAL ....................................................................................................................................... 1
3.1 References ........................................................................................................................... 1
3.2 Definitions .......................................................................................................................... 2
3.3 Responsibilities ................................................................................................................... 5
4.0 ALARA ............................................................................................................................................ 7
4.1 Policy Statement ................................................................................................................. 7
4.2 Administrative Implementation Procedures ....................................................................... 7
4.3 ALARA Committee ............................................................................................................ 8
5.0 EXPOSURE LIMITS....................................................................................................................... 8
5.1 Administrative Goals .......................................................................................................... 8
5.2 Occupational Exposure Limits ............................................................................................ 8
5.3 Embryo/Fetus Exposure Limits .......................................................................................... 9
5.4 Minor Exposure Limits ....................................................................................................... 9
5.5 Members of the Public Exposure Limits .......................................................................... 10
5.6 Air and Liquid Effluents ................................................................................................... 10
6.0 CONDUCT OF RADIOLOGICAL WORK .................................................................................. 10
6.1 Planning ............................................................................................................................ 10
6.2 Work Permits .................................................................................................................... 11
6.3 Control Zones ................................................................................................................... 11
7.0 MONITORING .............................................................................................................................. 13
7.1 Personnel Monitoring ....................................................................................................... 13
7.2 Workplace Monitoring ...................................................................................................... 14
7.3 Release of Materials from Contamination Areas .............................................................. 15
7.4 Instrument Calibration ...................................................................................................... 16
8.0 PERSONNEL PROTECTIVE EQUIPMENT ............................................................................... 17
8.1 Use and Selection of Protective Clothing ......................................................................... 17
8.2 Use and Selection of Respiratory Protection Devices ...................................................... 18
9.0 RADIOACTIVE MATERIAL ACCOUNTABILITY AND CONTROL ..................................... 18
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10.0 DECONTAMINATION ................................................................................................................ 19
10.1 Personnel ........................................................................................................................... 19
10.2 Equipment ......................................................................................................................... 19
11.0 WASTE MANAGEMENT ............................................................................................................ 20
12.0 EMERGENCY PROCEDURES .................................................................................................... 20
13.0 TRAINING .................................................................................................................................... 21
13.1 Radiological Worker Training .......................................................................................... 21
13.2 General Awareness Training ............................................................................................. 22
13.3 Visitors .............................................................................................................................. 22
14.0 AUDITS ......................................................................................................................................... 23
15.0 RECORDS MANAGEMENT ....................................................................................................... 23
List of Tables
Table 1 Occupational Dose Limits ................................................................................................................ 9
Table 2. Posting Requirements ................................................................................................................... 12
Table 3. Surface Radioactivity Release Limits ........................................................................................... 16
List of Appendices
Appendix A: Implementing Procedures ...................................................................................................... 20
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1.0 PURPOSE AND SCOPE
This Radiation Protection Plan (RPP) was prepared to implement the URS -Safety Management Standard
052, (SMS-052) “Radiation Protection Program,” at the Niagara Falls Storage Site (NFSS) Formerly
Utilized Sites Remedial Action Program (FUSRAP) Site. This plan provides detail on the work practices
necessary to fully implement SMS-052:
Activities at the project site where the potential for exposure to ionizing radiation exists are
conducted in a manner consistent with sound radiological practices,
Radiological exposure to site personnel and the environment are maintained As Low as
Reasonably Achievable (ALARA), and
Activities at this site are performed in a manner consistent with applicable NFSS FUSRAP
site requirements, local, state, and federal regulations.
2.0 APPLICABILITY
The work practices specified in this RPP apply to work conducted by site personnel that may result in the
exposure of employees to ionizing radiation. All URS site visitors, employees, and contractors doing
invasive working at NFSS or work with the potential for exposure to radiologically contaminated material
are responsible for following this RPP. The URS Project Manager (PM) and the Site Radiation Safety
Officer (SRSO) are responsible for ensuring that the RPP is implemented at the NFSS FUSRAP Site.
Implementation of this RPP will be performed through implementation of the Accident Prevention Plan
(APP), Site Safety and Health Plan (SSHP), and associated standard operating procedures.
3.0 GENERAL
3.1 References
URS Safety Management Standard – 052 Radiation Protection Program
DOT 49 CFR 171-177, Transportation – Hazardous Materials Regulations
NRC 10 CFR 20, Standards for Protection Against Radiation
OSHA 29 CFR 1910.1096, Ionizing Radiation
OSHA 29 CFR 1926.53, Ionizing Radiation
NRC Regulatory Guide 8.25
URS Safety Management Standard – 042 Respirator Protection
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US Army Corps of Engineers EM 385-1-80, Radiation Protection Manual
US Army Corps of Engineers EM 385-1-1, Safety and Health Requirements
US Army Corps of Engineers ER 385-1-80, Ionizing Radiation Protection ER 385-1-80,
Ionizing Radiation Protection
3.2 Definitions
Airborne Radioactivity Area – Area where the measured concentration of airborne radioactivity above
natural background exceeds a peak concentration of 1 derived air concentration (DAC) or 12 DAC-hours
during a workweek.
As Low As Reasonably Achievable (ALARA) – An approach to radiological control or a process to
manage and control exposures to the work force and to the general public at levels as low as is reasonable,
taking into account social, technical, economic, practical, and public policy considerations.
Bioassay – Measurement of radioactive material deposited within or excreted from the body. This process
may include whole body and organ counting as well as collection of urine and fecal samples.
Contaminated Area – An area in which radioactive contamination is present that exceeds removable
levels presented in Table 3.
Controlled Area – An area in which access is controlled in order to protect personnel from exposure to
radiation and radioactive materials. An area in which the existing or potential radiation and radioactivity
levels are above normal background but are less than that designating a radiological area or a restricted
area.
Derived Air Concentration (DAC) – The concentration of a radionuclide in air that, if breathed over the
period of a work year, would result in the annual limit on intake being reached.
Disintegration per Minute (dpm) – The rate of emission by radioactive material as determined by
correcting the counts per minute observed by a detector for background, efficiency, and window size
associated with the instrument.
Dose – A generic term for the amount of energy deposited in body tissue due to radiation exposure.
Technical definitions for dose terms necessary for various exposure calculations and recordkeeping
purposes include the following:
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Absorbed Dose (D) – Energy imparted to matter by ionizing radiation per unit mass of irradiated
material at the place of interest in that material. The units of absorbed dose are the rad and the
gray (Gy).
Dose Equivalent (HT) – The product of the absorbed dose in tissue, quality factor, and all other
necessary modifying factors at the location of interest. The units of dose equivalent are the rem
and sievert (Sv).
Effective Dose Equivalent (HE) – The sum of the products of the dose equivalent to the organ or
tissue (HT) and the weighting factors (WT) applicable to each of the body organs or tissues that
are irradiated (HE= SWTxHT).
Committed Dose Equivalent (HT,50) – The dose equivalent to organs or tissues of reference (T)
that will be received from an intake of radioactive material by a person during the 50-year period
following the intake.
Committed Effective Dose Equivalent (HE,50) – The sum of the products of the weighting
factors applicable to each of the body organs or tissues that are irradiated and the committed dose
equivalent to these organs or tissues (HE,50=SWTxHT,50).
Total Effective Dose Equivalent (TEDE) – The sum of the deep dose equivalent (for external
exposures) and the committed effective dose equivalent (for internal exposures).
Total Organ Dose Equivalent (TODE) – The sum of the deep dose equivalent (for external
exposures) and the committed dose equivalent to an individual organ or tissue (for internal
exposures).
Fixed Contamination – Radioactive material that cannot readily be removed from surfaces by
nondestructive means such as causal contact, wiping, brushing, or washing.
Frisking – Process of monitoring personnel and equipment for contamination.
Hazardous Work Permit (HWP) – Permit that identifies hazardous conditions and health and safety
hazards, establishes worker protection and monitoring requirements, and also contains specific approvals
for radiological work activities. The HWP serves as an administrative process for planning and
controlling both hazardous and radiological work.
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High Radiation Area – An area, accessible to personnel, in which radiation levels could result in a
person receiving a dose equivalent to or in excess of 100 mrem in 1 hour at 30 cm from the radiation
source or from any surface that the radiation penetrates.
Internal Dose – The portion of the dose equivalent received from radioactive material taken into the
body.
Occupational Dose – The dose received by a person during employment in which the person’s assigned
duties involve exposure to radiation and to radioactive material. Occupational dose does not include dose
received from background radiation, as a patient from medical practices, from voluntary participation in
medical research plans, or as a member of the public.
Optically Stimulated Luminescence Dosimeter (OSL) – Radiation detection and measuring device
used to record the radiological exposure of personnel or area to certain types of radiation.
Personnel Dosimetry – Devices designed to be worn by a single person for the assessment of dose
equivalent such as film badges, optically stimulated luminescence dosimeter, and pocket ionization
chambers.
Personnel Monitoring – Systematic and periodic estimates of radiation dose received by personnel
during work hours.
Radiation Work Permit (RWP) – Permit that identifies radiological conditions, establishes worker
protection and monitoring requirements, and contains specific approvals for radiological work activities.
The RWP serves as an administrative process for planning and controlling radiological work and
informing the worker of the radiological, health and safety issues.
Radioactive Material Area – A controlled area or structure where radioactive material is used, handled,
or stored.
Radiation – Ionizing radiation that includes alpha particles, beta particles, X-rays, gamma rays, neutrons,
and other particles capable of producing ions.
Radiation Area – An area, accessible to individuals, in which radiation levels could result in an
individual receiving a dose equivalent or in excess of 5 mrem in 1 hour at 30 cm from the source of
radiation or from any surface that the radiation penetrates.
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Radiological Controlled Areas (RCA) – Include Radiation Areas, Contamination Areas, or Airborne
Radioactivity Areas.
Radiological Worker – Worker whose job assignment requires work on, with, or in the proximity of
radiation production machines or radioactive materials. A radiological worker has the potential of being
exposed to more than 100 mrem per year, which is the sum of the dose equivalent to external irradiation
and the committed effective dose equivalent to internal irradiation.
Removable Contamination – Radioactive material that can be removed from surfaces by nondestructive
means, such as casual contact, wiping, brushing, or washing.
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 source of radiation. When
appropriate, such an evaluation includes a physical survey of the location of radioactive material and
measurements or calculations of levels of radiation, or concentrations or quantities of radioactive material
present.
Unrestricted Area – An area designated by the Nuclear Regulatory Commission (NRC) as being an area
to which access is neither limited nor controlled by an NRC licensee.
3.3 Responsibilities
3.3.1 Project Manager
The URS PM is responsible for:
Reviewing each scope of work to identify potential radiation risks and hazards.
Designating an SRSO and arranging for employees on the project to receive appropriate
radiation safety training.
Ensuring that employees working on the project are monitored for radiation exposures.
Assessing and controlling risks to employee and public health and safety from site activities.
The URS PM will ensure that all employees are knowledgeable of applicable radiological safety
requirements for their work area and compliance with these requirements. PMs emphasize the need for
high standards for radiological control through direct communication, support of radiation control goals
and a presence in the workplace.
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3.3.2 Project Certified Health Physicist
The Project Certified Health Physicist (CHP) is responsible for:
Reviewing and approving the RPP.
Reviewing and approving implementing radiation procedures.
Reviewing and approving radiation safety training materials for employees.
Reviewing dose calculations.
3.3.3 Site Radiation Safety Officer
The SRSO is responsible for:
Coordinating implementation of the Radiation Protection Program.
Developing and administering the RPP incorporated in the SSHP and associated standard
operating procedures.
Evaluating potential site/employee radiation exposure.
Recommending necessary workplace and administrative controls.
Conducting radiation safety training.
Issuing RWPs/HWPs.
Administering personnel monitoring program.
Arranging for each individual’s monitoring results to be sent to the individuals and employers
as appropriate.
3.3.4 Radiation Technicians
Radiation Technicians are responsible for assisting the SRSO in implementing the radiological controls
on each site. Specific responsibilities include:
Performing routine radiological surveys (i.e., incoming equipment, outgoing equipment,
DOT, excavation control).
Collecting and counting smears, assisting in sample collection.
Collecting required field investigation radiation measurements.
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In conjunction with the SRSO, assessing radiological hazards during work changes and
making adjustments to ensure that worker radiological exposures and releases to the
environment are maintained ALARA.
The SRSO will review the qualifications of Radiation Technicians to ensure that the level of expertise is
commensurate with the assigned duties.
3.3.5 Employees
Employees are responsible for knowing radiological protection requirements for their work areas and for
complying with these requirements.
4.0 ALARA
4.1 Policy Statement
All work with ionizing radiation will be conducted in accordance with established good practices in
radiation protection, and in all cases, incorporate radiological criteria to ensure safety and maintain
radiation exposures ALARA. The primary method to maintain exposure ALARA will focus on the use of
established work practices and facility and equipment design features. These features will be augmented
with the use of administrative and procedural requirements. In most cases, decontamination operations
represent an uncommon activity.
4.2 Administrative Implementation Procedures
The following minimum steps will be implemented on all sites aimed at maintaining radiation exposures
ALARA.
Estimate radiation exposure and use the estimate to set project ALARA dose goals.
Review actual radiation exposures and compare with projected dose values. If necessary,
make adjustments to the administrative and engineering control in place.
Commensurate with the nature of the work being performed and radiation levels present, the following
additional measures will be considered:
Inclusion of radiation control hold points in work documents;
Work processes and special tools to reduce exposures;
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Engineering controls to minimize the spread of activity;
Special radiological training or monitoring requirements;
Engineering, design, and use of temporary shielding;
Walkdown or dry-run of the activity using applicable procedures; and
Staging and preparation of necessary materials/special tools.
4.3 ALARA Committee
An ALARA Committee will be formed and will be minimally comprised of the SRSO, the URS PM, and
one representative of the site labor force. The ALARA Committee will meet periodically (at least once
each quarter) and will review past site radiation data, or personnel exposures, air monitoring, effluent
monitoring, and contamination level data to assess the presence of unacceptable trends. Due to the
schedule for this project, the Committee will meet at once. Additionally, this Committee will periodically
assess the success of the radiological controls and serve as a forum for recommendations for
improvements. A written record of the Committees activities will be maintained.
5.0 EXPOSURE LIMITS
5.1 Administrative Goals
Administrative goals for radiological protection performance will be established. These limits for workers
are more conservative than regulatory limits, commensurate with the work plan and level of hazard, and
in accordance with the ALARA principle. The annual radiological goals include (not to exceed):
Maximum individual total effective dose equivalent – 500 mrem/yr;
Maximum embryo/fetus total organ dose equivalent for a declared pregnancy – 100 mrem/
gestation; and
Maximum total effective dose equivalent to a member of the public, or visitor (excluding
radon and thoron) – 100 mrem/yr.
5.2 Occupational Exposure Limits
The occupational exposure to employees performing the duties of radiation workers will be controlled so
that the limits in Table 1 (below) are not exceeded in one year. Furthermore, measures will be taken to
maintain doses as far below these limits as reasonable achievable through use of administrative goals,
engineering controls, and application of the ALARA process. All of the occupational exposure received
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during the year, including exposure while employed elsewhere, will be included in the determination of
occupational exposure. Radiation exposure from normal background, therapeutic and diagnostic medical
radiation, and voluntary participation in medical research plans will not be included in determining
occupational exposure. Planned special exposures will not be required.
Table 1. Occupational Dose Limits
Category URS ALARA Limit 10 CFR 20 Limit mrem/yr mSv/yr mrem/yr mSv/yr
Total Effective Dose1 500 5 5,000 50 Total Organ Dose Equivalent 5,000 50 50,000 500 Lens of Eye 1,500 15 15,000 150 Shallow Dose 5,000 50 50,000 500
Embryo/Fetus 100/gestation 1/gestation 500/gestation 5/gestation Minor N/A N/A 500 5 General Public 100 1 100 1
1 In addition to the annual dose limits, soluble uranium intake will be limited to 10 milligrams in a week in consideration of chemical toxicity.
5.3 Embryo/Fetus Exposure Limits
The occupational dose equivalent limits applicable to the embryo/fetus are detailed in Table 1, and apply
to a "declared pregnancy." In such a case, a woman may elect to declare the pregnancy and limit the dose
received by the embryo/fetus as provided in regulatory requirements. In this case, the dose equivalent
goal for the embryo/fetus, from the period of conception to birth from occupational exposure, will be no
more than 100 mrem.
Efforts shall be made to maintain exposures ALARA and to avoid significant variations above a uniform
monthly exposure during the pregnancy. If the dose equivalent has exceeded 500 mrem at the time the
pregnancy is declared, steps shall be taken to ensure that additional occupational exposure is unlikely.
SMS Attachment 52-4, Declaration of Pregnancy Form, will be used to document this decision. SMS
Attachment 52-5, Embryo/Fetus Initial Dose Calculation, will be used to assess the radiation exposure to
the embryo/fetus at the time of declaration. SMS Attachment 52-6, Withdrawal of Pregnancy Declaration,
will be used to withdraw a pregnancy declaration.
5.4 Minor Exposure Limits
URS policy is that no worker under 18 years of age will be allowed to work on site where there is the
potential for exposure to radiation.
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5.5 Members of the Public Exposure Limits
The annual exposure limit for any member of the public shall be limited to 100 mrem total effective dose
equivalent, regardless of whether the individual is inside or outside of a controlled area. The dose
equivalent in any unrestricted area from external sources will not exceed 2 mrem in any one hour or
50 mrem per year, regardless of occupancy by a member of the public.
5.6 Air and Liquid Effluents
The release of radioactivity in air or liquid effluents to unrestricted areas will be monitored and controlled
in accordance with the requirements of 10 CFR 20.1302. Projects that are subject to state or local
regulatory requirements will comply with the effluent limitations in those requirements. For projects at
low-hazard sites, workplace monitoring and/or conservative modeling can be used to determine
compliance with effluent limitations. Records of air monitoring, radioactive effluent monitoring, and/or
modeling will be generated and maintained to demonstrate compliance with effluent limitation
requirements.
6.0 CONDUCT OF RADIOLOGICAL WORK
6.1 Planning
Incorporating radiological protection requirements such as engineering controls and dose and
contamination reduction considerations are key to the successful execution of work activities in areas
where there is a potential for exposure to radiation or radioactive materials. Reviewing and incorporating
such controls and considerations will be made on a site-by-site basis and will be commensurate with the
quantity and type of radioactive materials present. Appropriate requirements will be documented in
applicable work plans and procedures.
Projected radiation dose (internal and external) estimates will be made for all jobs involving potential
exposure to radiation or radioactive materials. The complexity of these exposure estimates will be
commensurate with the levels of radiation and radioactive materials present and the types of activities
involved. Documentation of these exposure estimates will be placed in the project file.
Trigger levels for the development and execution of ALARA reviews will be adopted on a site-specific
basis and documented. At a minimum, ALARA reviews will be conducted any time projected individual
dose exceeds 200 mrem, or collective dose estimates exceed 2,000 person-mrem.
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6.2 Work Permits
URS uses a Radiation Work Permit (RWP) process to detail specific requirements for work activities, as
defined in SMS 052. RWPs (see SMS Attachment 52-2) will be used to inform workers of area
radiological conditions and entry requirements, and to provide a mechanism to relate worker exposure to
specific work activities. They will be used at all sites that have a potential for exposure to radiation or
radioactive materials. If appropriate, radiological requirements will be combined with other, non-
radiological requirements, onto a single HWP (see SMS Attachment 52-3). Implementation of a work
permit plan will have the following minimum requirements:
RWPs/HWPs will be written based on radiological survey data that are appropriate to
characterize the expected work conditions.
RWPs/HWPs will detail the work area and activity that are within their scope and will specify
requirements for protective measures, including dosimetry, air sampling, PPE, respiratory
protection, work area preparation, and health physics oversight.
RWPs/HWPs will be reviewed and approved by the SRSO. Modifications to existing
RWPs/HWPs will require the concurrence of the SRSO or designee.
RWPs/HWPs will be readily available in the work area (if access control points are
established the RWP/HWP will be posted at the access point to the applicable radiological
work area).
Workers will acknowledge by signature that they have read, understand, and will comply
with the RWPs/HWPs prior to initial entry to the area and after any revisions to the
RWPs/HWPs.
RWPs/HWPs will be updated if radiological conditions change to the extent that protective
requirements need modification.
6.3 Control Zones
6.3.1 Access/Egress Procedures
Only appropriately trained, authorized, and qualified personnel will be permitted access to radiological
controlled areas. The degree of control will be commensurate with the existing and potential radiological
hazards within the area and may include, for example, signs and barricades, entrance ways locked against
ingress, control devices or alarms, or administrative controls. The establishment of High or Very High
Radiation Areas is not anticipated for this project; however, additional access control measures for High
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and Very High Radiation Areas will be established in accordance with 10 CFR 20, as appropriate. The
controls will be established so that rapid egress from the controlled area in an emergency is not prevented.
Control measures and established procedures will incorporate a RWP/HWP system to ensure appropriate
planning, control, hazard communication, and documentation of work activities in Radiological
Controlled Areas (RCA) that include Radiation Areas, Contamination Areas, or Airborne Radioactivity
Areas. Task-specific RWP/HWP s will be used for short-term work in these RCAs with the potential for
changing radiological conditions. General RWP/HWP’s may be used for longer term activities in RCAs
with known, stable radiological conditions.
Personnel frisking and/or monitoring will be conducted before exiting radiologically contaminated areas
and other areas where there is a potential for contamination.. If the instruments indicate greater than
100 cpm above background, a Radiation Technician will be contacted for decontamination of personnel.
6.3.2 Posting and Labeling
The standard radiation symbol (ANSI N2.1/12.1) in magenta or black on a yellow background (or
alternate as provided by regulations) will be used to warn individuals of the presence of radiation and/or
radioactive material. Each access point to a controlled or restricted area will be posted with the
appropriate identification and instructions. For controlled or restricted areas, each area will be posted as
detailed in Table 2 below.
Table 2. Posting Requirements Posting Sign Definition Caution Radiation Area 5 mrem in 1 hour at 30 cm Caution-High Radiation Area or Danger High Radiation Area
100 mrem in 1 hr at 30 cm
Grave Danger-Very High Radiation Area 500 rads in 1 hr at 1 m Caution Contaminated Area Removable radioactive contamination in excess of Table 3
values Caution Airborne Radioactivity Area or Danger Airborne Radioactivity Area
>1 DAC or 12 DAC hours/week
Caution, Radioactive Material or Danger Radioactive Material
Radioactive material handled, used or stored
Additionally, NRC Form 3, "Notices to Employees," will be posted in a location visible to all employees who work with or around radioactive materials.
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7.0 MONITORING
7.1 Personnel Monitoring
7.1.1 Internal Dosimetry
All personnel who have the potential to receive intakes of radioactive materials that may result in a
committed effective dose equivalent (HE, 50) of 500 mrem will participate in an appropriate bioassay
plan. This plan will be reviewed and approved by a qualified Health Physicist and will be capable of
detecting internal radioactive materials at a level below 10% of the Annual Limit of Intake listed in
Appendix B of 10 CFR 20 for each radionuclide for which exposure at this level is likely.
Prior to commencement of work in restricted or controlled areas with the potential for internal exposure in
excess of the levels stated above, each radiation worker will have an appropriate baseline bioassay
performed. These individuals will also have an appropriate exit bioassay performed when they leave the
project.
All personnel who perform routine field activities where the potential for removable surface or airborne
radioactive contamination exists will participate in an appropriate routine bioassay plan. Special follow-
up bioassay procedures will be implemented whenever a suspected intake has occurred or routine
bioassay results are above a derived investigation level. The bioassay plan for NFSS includes the
collection of pre and post work urine samples for uranium analysis.
7.1.2 External Dosimetry
Monitoring applies to any individual likely to receive an annual external whole body exposure in excess
of 10% of the occupational limit. All personnel dosimetry used will be processed and evaluated by a
processor holding a current accreditation under the National Voluntary Laboratory Accreditation Plan
(NVLAP) of the National Institute of Standards and Technology (NIST).
Personnel dosimetry will be issued to URS and subcontractor personnel who are assigned to work at the
site during invasive activities, or when working with potentially contaminated material.
7.1.3 Summation of Internal and External Exposures
Internal committed effective dose equivalents and external effective dose equivalents during the year will
be combined to determine the annual total effective dose equivalent in accordance with the requirements
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of federal and state regulations. Generally, summation will be required when intakes exceed 10% of the
annual limit on intake, may result in a total effective dose equivalent of 50 mrem for minors or visitors, or
a dose equivalent of 50 mrem to the embryo/fetus for declared pregnant women. The deep dose
equivalent to the whole body may be used as the effective dose equivalent for external exposures.
7.1.4 Medical Surveillance
No specific medical surveillance requirements exist for exposure to radiation levels at occupational levels.
General medical surveillance requirements for all hazardous waste sites are contained in the SSHP.
All cases of overexposure and suspected ingestion or inhalation of radioactive materials must be reported
to the SRSO immediately. The URS Medical Consultant will advise the SRSO on the type(s) of test(s)
required to accurately assess exposure effects.
7.2 Workplace Monitoring
7.2.1 Surveys
Radiological monitoring and surveys of radiation exposure levels, contamination, and airborne
radioactivity will be conducted to:
Characterize workplace conditions and detect changes in those conditions;
Verify the effectiveness of physical design features, engineering and process controls, and
administrative control procedures;
Demonstrate regulatory compliance;
Detect the gradual buildup of radioactive material;
Identify and control potential sources of personnel exposure; and
Identify areas requiring postings.
Monitoring will be performed only by trained and qualified personnel, following RP 4.0 Radiation
Surveys and RP 5.0 Smear Counter Setup and Operation. Monitoring will be conducted as specified in the
SSHP and associated RWPs.
Minimally, radiological surveys will be conducted:
During the establishment of controlled areas;
Weekly in active controlled areas, radiation and/or contamination areas;
15 October 2013
Monthly, or upon access in inactive controlled areas;
As specified on RWPs/HWPs; and
During the release of controlled areas.
7.2.2 Air Sampling
General area and personal air sampling will be conducted in accordance with the guidance in NRC
Regulatory Guide 8.25. Air sampling will be employed when necessary to determine whether
confinement of radioactive material is effective, to determine workplace administrative controls required,
estimate worker intakes, and determine what personal protective equipment (PPE) is appropriate.
General area air sampling for airborne radioactivity will be conducted with high-volume air samplers
where the potential for airborne radioactivity is above background levels. High-volume air samplers are
those with sufficient flow rate to achieve a minimum detectable activity (MDA) of 10% of the applicable
DAC in an 8-hour shift. For small jobs with documented minimal airborne radioactivity potential, general
area air sampling for airborne radioactivity will not be required. Air samples will be analyzed in
accordance with written procedures. In areas with a potential for short-term airborne excursions,
representative grab samples will be collected in the immediate vicinity of work being performed to
determine whether the area is an airborne radioactivity area requiring additional work controls and if
personal breathing-zone air sampling is necessary to assess the worker's intake of airborne radioactive
materials. As with the protocol for personal sampling, high-volume sample results will be compared with
the appropriate DAC.
When required to estimate worker intakes, representative personal air sampling from each field team
working in radiologically contaminated areas will be conducted for airborne radioactivity in the breathing
zone. The data will be compared with the DACs that are appropriate for the contaminant(s) expected to be
present to gauge employee exposure potential. DACs for radioactive contaminants in Appendix B to 10
CFR 20 will be used to assess exposure potentials, as appropriate.
7.3 Release of Materials from Contamination Areas
Radiological contamination survey, documentation, and labeling requirements will be established for all
property/material released from an RCA. All equipment, materials, and property used in an RCA
established for contamination control will be considered as potentially contaminated and will not be
16 October 2013
released to an uncontrolled or unrestricted area until they have been surveyed and meet the unconditional
release limits listed in Table 3 below, or approved alternative site-specific requirements.
Table 3. Surface Radioactivity Release Limits Acceptable Surface Contamination Levels Nuclidea Averageb,c Maximumb,d Removableb,e U-nat, U-235, U-238, and associated decay products
5,000 dpm α/100 cm2 15,000 dpm α/100 cm2 1,000 dpm α/100 cm2
Tranuranics, 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
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 β-γ/100 cm2
15,000 dpm β-γ/100 cm2
1,000 dpm β-γ/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 tape, 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.
If the property/material to be released either cannot be monitored using standard survey techniques or is a
volume or bulk material, such as liquids, soils, and so forth, it will be considered potentially
contaminated. A special property/waste release evaluation will be conducted prior to release. The release
limits for these materials will be established in accordance with specific guidance from the cognizant
regulatory authority. All surveys and evaluations for release of potentially contaminated property/material
to uncontrolled or unrestricted areas will be documented.
7.4 Instrument Calibration
Radiation detection instrumentation will be provided as appropriate for performing necessary surveys and
monitoring. The instrumentation will be selected based upon the type of radiation detected, MDA
measurement capability, and range in accordance with the radiological hazards present or anticipated for
the project.
17 October 2013
The vendor or a calibration service will perform calibration of radiological instruments and equipment in
accordance with ANSI N323 (1997) using standards traceable to the NIST primary standards. The
calibration certificate will be maintained by the SRSO.
Field calibration of counting instrumentation in accordance with approved written procedures is
authorized if it meets the above requirements and the source calibration certificate and documented
detection efficiency determination are maintained in the site-specific project file. Each instrument or piece
of equipment will have a calibration sticker with an expiration date affixed.
At a minimum, performance tests of radiological instruments will be conducted before use. Satisfactory
performance test results will be within ±20% of the expected response. Instruments that do not meet
performance test criteria, are found to be out of calibration, or are defective, will be removed from service
until repaired and/or calibrated. The results of these checks will be recorded in a daily source check log
by the performer and will be maintained in the project file. All performance tests will be conducted in
accordance with approved written procedures.
8.0 PERSONNEL PROTECTIVE EQUIPMENT
8.1 Use and Selection of Protective Clothing
PPE will be selected based on the contamination levels in the work area and the anticipated work activity,
ALARA and safety considerations, and consideration of non-radiological hazardous materials that may be
present. Surfaces are considered radiologically contaminated if above Table 3 levels. PPE provided will
be in good condition and free of chemical or radioactive contamination.
Full Set
Coveralls (Tyvek ® or cotton)
Cotton glove liners
Rubber or chemical resistant gloves
Shoe covers
Protective overshoes
Protective clothing and equipment selected for project tasks will be described in the SSHP, together with
procedures for donning and removing PPE without spreading contamination or contaminating the worker.
The necessary PPE for a task will be specified by the RWP.
18 October 2013
8.2 Use and Selection of Respiratory Protection Devices
URS Respiratory Protection SMS -042 details specific procedures for respiratory usage, fit, cleaning, and
so forth.
Engineering control measures will be provided to limit the concentrations of radioactivity in air to levels
below those that constitute an airborne radioactivity area to the extent feasible. When this level is not
feasible, other methods such as administrative controls and respiratory protection will be employed to
limit the potential for intake of radioactive material.
Only respiratory protection equipment that is tested and certified by the National Institute for
Occupational Safety and Health (NIOSH) will be used. Protection factors listed in Appendix A of 10 CFR
20 will be used in the assessment of potential radioactive material intake.
Selection of appropriate respiratory protection devices will be designated within either the SSHP or the
RWP. Selected respiratory protection devices will have as a minimum a protection factor greater than the
multiple by which peak concentrations or airborne radioactivity exceed the values specified in Appendix
B of 10 CFR 20. Only respiratory protection equipment that has been specifically certified for emergency
use by NIOSH/Mine Safety and Health Administration (MSHA) will be used as emergency devices.
Whenever respiratory protection will be used at a site, the following additional minimum requirements
will be met:
Air sampling will be performed to identify the potential hazard, permit proper equipment
selection, and estimate exposures.
Surveys and bioassays as appropriate will be performed to evaluate actual intakes.
Respirators will be tested for operability immediately prior to each use.
Written procedures will be available regarding selection, fitting, issuance, maintenance, and
testing of respirators (including testing for operability prior to each use), supervision and
training of personnel, monitoring (including air sampling and bioassays), and recordkeeping.
9.0 RADIOACTIVE MATERIAL ACCOUNTABILITY AND CONTROL
All procurement, receipt, and storage of radioactive material will be coordinated with the individual or
organization responsible for radiation protection at the project site. A source custodian and documented
inventory record will be established and maintained for radioactive sources. All sources brought on site
19 October 2013
by external organizations will not be allowed into areas under company control without prior notification
and approval by the company individual or organization responsible for radiation protection. Radioactive
materials licenses will be required for sources that exceed exempt quantities.
Transportation of radioactive material (specific activity >2000 pCi/g) in commerce, generally off site, will
be in accordance with Department of Transportation (DOT) requirements in 49 CFR 170 through 180,
and other federal, state, and local regulations, as applicable.
10.0 DECONTAMINATION
10.1 Personnel
The guideline for determining the presence of skin contamination on personnel is detectable radiological
contamination above background.
If necessary, decontamination of personnel will be performed only under the direct supervision of the
SRSO. Generally, dry, nonabrasive methods will be attempted first and, if necessary, may be followed by
washing with soap and water. Material generated during decontamination, including wipes, tape, and
water, will be collected and disposed of as radioactive waste. Specific decontamination procedures and
documentation requirements are contained in site-specific standard operating procedures (SOPs). Non-
radiological decontamination procedures are contained within the SSHP.
10.2 Equipment
Surface contamination criteria presented in Table 3 will be used to determine if a piece of equipment is
contaminated with radioactive materials. When decontamination is necessary, decontamination will be
performed using techniques that are appropriate based on site-specific conditions. Generally, dry
decontamination methods such as high-efficiency particulate air (HEPA) vacuuming or wipedowns are
preferred when facilities for the collection of radiological contaminated wastewater are not in place. If
adequate facilities exist for the collection of such fluids, it may be appropriate to use a wet
decontamination technique. Additional decontamination methods include sand or other abrasive blasting.
Specific decontamination procedures and decontamination requirements are contained in the site-specific
SOPs. Non-radiological equipment decontamination procedures are contained in the SSHP.
20 October 2013
11.0 WASTE MANAGEMENT
Radioactively contaminated waste material generated during this project will be managed in accordance
with the EM-1110-35-1, “Management Guidelines for Working with Radioactive and Mixed Waste, and
the project-specific work plan. Materials suspected of being mixed waste (RCRA/TSCA/etc. hazardous
substances combined with radioactive materials) will be identified and segregated as soon as practical to
avoid combining mixed waste with other waste forms.
While the scope of this waste minimization plan will be commensurate with the level of radioactive
materials present and activities conducted at each site, at a minimum, the following guidelines will be
used:
Removal of excess/unnecessary packaging material prior to bringing materials into
radiological controlled areas;
Restriction of materials entering radiological areas to those materials necessary for
performance of work;
Restriction of the quantities of hazardous materials, such as paints, solvents, chemicals,
cleaners, and fuels, entering radiological areas;
Substitution of reusable items in place of disposable ones, when practical;
Selection of consumable materials such as PPE that is compatible with waste processing
systems, volume reduction, and waste acceptance criteria;
Survey of potentially contaminated material leaving controlled areas to separate
uncontaminated materials from contaminated materials; and
Emphasis on waste reduction methodologies in training.
Additional waste minimization procedures and/or requirements will be identified in each site-specific
work plan and will be commensurate with the levels of radioactive materials present and activities being
performed.
12.0 EMERGENCY PROCEDURES
Details on the site-specific emergency procedures are provided in the SSHP. At a minimum, emergency
procedures will take into account client emergency response procedures and the responsibilities of off-site
state and local emergency response agencies. All site personnel will be instructed in their emergency
responsibilities and the emergency procedures.
21 October 2013
13.0 TRAINING
Training will be provided to general employees, radiation workers, and radiological control staff at a
project site under this RPP. Periodic retraining will be conducted whenever a significant change to the
RPP or implementing procedures occurs or at a frequency consistent with applicable regulatory or client
requirements and commensurate with radiological hazards present on the site. Minimum retraining
frequency of two years will be implemented.
All formal training under the RPP will verify individual knowledge by an appropriate examination.
Documentation of training will be generated containing the individual’s name, date of training, topic(s)
covered, pass or fail, and the name of the certifying official. No employee will be permitted to
independently perform tasks inside of a radiological controlled area until the appropriate training and
qualification requirements are met.
Additional training requirements will be determined on a site-specific basis and will be commensurate
with the radiological hazards present on each site. These additional requirements will be documented in
the SSHP.
13.1 Radiological Worker Training
At a minimum, all personnel entering an area where radioactive material or radiation generating devices
are used, and where there is a potential for an individual to receive a Total Effective Dose Equivalent
(TEDE) of 100 mrem or more in one year, will receive the following training:
Radiological Fundamentals – Atomic Structure, Definitions and Units of Measure, the Four
Basic Types of Ionizing Radiation, Units of Measure for Radiation.
Biological Effects – Sources of Radiation, Effects of Radiation on Cells Acute and Chronic
Radiation Dose, Prenatal Radiation Exposure, Risks in Perspective.
Radiation Dose Limits – Basis for and Purpose of Radiation Dose Limits and,
Administrative Control Levels, and Worker Responsibilities Regarding Dose Limits.
ALARA Program – ALARA Program, Responsibilities for the ALARA Program, External
and Internal Dose Reduction, Radioactive Waste Minimization.
Personnel Monitoring Programs – External Dosimetry, Internal Monitoring, Methods for
Obtaining Radiation Dose Records.
22 October 2013
Radiological Access Controls and Postings –Radiological Work Permits, Radiological
postings, Requirements for entering, working and exiting Radiological Control Areas.
Radioactive Contamination – Types and sources of contamination, Contamination control
methods, Contamination monitoring equipment, Decontamination
Radiological Emergencies – Emergency Alarms and Responses, Radiological Emergency
Situations, Considerations in Rescue and Recovery Operations.
Practical Factors – Review an Appropriate Radiological Work Permit (RWP), Record the
Appropriate Information on the RWP, Select and Wear Required Dosimeter(s), Enter
Simulated Area and Demonstrate ALARA Techniques, Monitor for Contamination, Respond
to Emergency Situations or Abnormal Radiological Situations.
13.1.1 Authorized Users
Authorized Users (AU) are individuals who, by their training and experience, are allowed to work,
unsupervised, with radioactive material or radiation generating devices, and also directly supervise
Authorized Users Assistants working with radioactive material. Training for Authorized Users will
include eight hours of classroom training on the topics detailed above in addition to the practical factors.
13.1.2 Authorized User Assistants
Authorized User Assistants (AUA) are individuals allowed to work with radioactive material only under
the direct supervision of an AU (that is, in the physical presence of the AU).Training for AUA will
include four hours of classroom training on the topics detailed above in addition to the practical factors.
13.2 General Awareness Training
General employees who are not radiation workers but may be involved in an occasional or indirect
manner with radioactive material or activities supporting decontamination and decommission (D&D)
efforts will receive training specific to the site activities. This training will be similar in content to the
radiation worker training but will not require a practical exercise.
13.3 Visitors
Visitors to the site will be escorted by a trained Authorized User and will not be allowed unescorted
access to radiation areas.
23 October 2013
14.0 AUDITS
An internal audit of the field implementation of this RPP will be conducted at least once per year by the
SRSO. Audit findings will be reported in writing to appropriate personnel and agencies.
15.0 RECORDS MANAGEMENT
RPP records will be maintained to document compliance with regulatory requirements and the exercise of
due diligence in the control of radiological hazards for the protection of employees, members of the
public, and the environment. These records will be transferred to the project file at the conclusion of the
project.
At the completion of site activities, copies of exposure monitoring records will be sent to the individuals
monitored and their employers where appropriate. URS employees will have copies also sent to the URS'
Health Services Administrator for inclusion into each respective employee’s medical file. Exposure
monitoring records for subcontract personnel will be transferred to each respective subcontract
organization. Monitored individuals will be provided with a copy of their radiation monitoring results,
consistent with the requirements of 10 CFR 19.13. Upon completion of work at a site, exposure data
pursuant to the 10 CFR 19.13 requirement will be provided for URS employees only. Subcontract
personnel will be required to make requests for exposure records directly to their respective employer.
Exposure records that are maintained by URS will be maintained in a manner consistent with applicable
Privacy Act requirements. The records will be available for retrieval over a period not less than 75 years
after the date of creation of the record. All quantities used in the records will be in special units of curie,
rad, or rem, including multiples and subdivisions of these units. Records identified with an individual's
name or identifying number will be available upon request from that individual.
Records to be maintained include the following (as available):
Doses received by individuals, for whom monitoring was required, during previous
employment;
Doses received by individuals for whom monitoring was required;
Dose assessments and organ burdens for individuals for whom bioassay was performed;
Doses to the embryo/fetus of a declared pregnant employee;
Written declarations of pregnancy;
Written withdrawal of declaration of pregnancy;
24 October 2013
Results of surveys for radiation and radioactive material in the workplace and outside of
controlled or unrestricted areas as required by regulatory requirements or the radiation
protection program;
Results of surveys for the release of material or equipment to uncontrolled or unrestricted
areas;
Records of effluents and radioactive waste disposal under control;
Results of calibrations performed on radiological instruments and quality control checks for
radiological instrumentation and personal monitoring devices;
Records of ALARA evaluations and control actions;
Records of radiological training completed, including general employee radiological training;
Records of internal reviews and audits with corrective actions closeout; and
Records of regulatory agency inspections and audits with corrective actions closeout.
Interim storage of the above radiological records will be the responsibility of the SRSO and will be
maintained in a readily retrievable, controlled manner. Upon completion of each site project, and upon
request, copies of all radiation exposure records will be made available to appropriate parties.
Records associated with radiation surveys and measurements performed to support activities associated
with D&D of a site and equipment are:
Name of the person making the evaluation and recording the results;
Date of the survey;
Instrument serial number used for surveys and measurements; and
Results obtained.
URS will record contamination levels observed and procedures followed for incidents involving
contamination of individuals. The record should include name of individuals involved, description of
work activities, calculated dose, probable causes (including root causes), steps taken to reduce future
incidents of contamination, times and dates, and the surveyor’s signature.
Appendix A: Implementing Procedures
Table of Contents
RP-1.0 Personnel Monitoring
RP-2.0 Issuing RWPs and HWPs
RP-3.0 Portable Survey Instruments
RP-4.0 Radiation Surveys
RP-5.0 Smear Counter Setup and Operation
RP-6.0 Sample Handling and Chain of Custody
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RP 3
1 Page 1
August 29, 2
Date
August 29, 2
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RP 3
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ABLE SUTRUMEN
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RP 3
1 Page 4
response. Setg.
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RP 3
1 Page 5
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RP
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3.0
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Instrument(Mfg/Mdl
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Source Name
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Detailed description
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Bkgd
ading Units Readi
cpm
cpm
cpm
cpm
cpm
cpm
cpm
cpm
cpm
cpm
cpm
cpm
E SURVEY IN
ource Check F
Serial #
Serial #
HV
Due
Assay Date
Activity
er notes
Source
ing Units Ok?
cpm
cpm
cpm
cpm
cpm
cpm
cpm
cpm
cpm
cpm
cpm
cpm
NSTRUMEN
Form
Net
Reading Units O
cpm O
cpm O
cpm O
cpm O
cpm O
cpm O
cpm O
cpm O
cpm O
cpm O
cpm O
cpm O
NTS Issue
AugustRevis
Av
To
±
Notes Ok?
Ok
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Ok
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Date t 2013
R
sion 1 Pa
Initial QC Se
Source B
1
2
3
4
5
6
7
8
9
10
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olerance
± 20%
RP 3.0
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Purpose To provide a adiation leve
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RADIA
Site Radiatio
Certified Hea
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ATION SU
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radiation surtion equipme
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oors, with parfaces to be sand drains s
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August 29, 2
Date
August 29, 2
Date
ea with eleva
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4.0
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d, or areas we soil/surfaceents may be the conditio
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RADIA
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Issue DaAugus2013
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stigation lev
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Issue DaAugus2013
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Site Yr Ty
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001
Project Na
Survey #
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RADIA
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Issue DAugust 2Revisio
Date 2013
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RP 4.0
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All readings in c
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R SETUP ION
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Issue DatAugust 20Revision
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2929 attacheta. Typically
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RP 5
1 Page 1
August 29, 2
Date
August 29, 2
Date
contaminatit is not wanter surveys prod contribute d beyond the
be verified ental compaion. The perform the
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5.0
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2013
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Complete sources us
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COUNTERD OPERATI
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Issue DatAugust 20Revision
sheet tab labeiciency, minierational che
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RP 5
1 Page 2
eled Counteimum detecteck criteria. eadsheet are
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3.4.9
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Table 1: Ch
N-1
2 3 4 5 6 7 8 9
10 11 12 13 14 15 16 17 18 19
SMEAR CAND
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X2 0.975
5.02 7.38 9.35
11.1 12.8 14.4 16.0 17.5 19.0 20.5 21.9 23.3 24.7 26.1 27.5 28.8 30.2 31.5
R SETUP ION
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Issue DatAugust 20Revision
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count rate. T
m the numbe
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rements
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0010 0506 216 484
31 24 69
8 70 25
2 40 01 63 26 91
6 23
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RP 5
1 Page 3
nt. Note that
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This result is
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5.0
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3.6.1
Table 1: Ch
N-1
20 21 22 23 24 25 26 27 28 29 30 31 41 51 61 71 81 91
101
nt Efficiency
3.5.1 Inskno
3.5.2 Thbac
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strument effiown value.
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strument hasthe MDA an
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COUNTERD OPERATI
Values for N
X2 0.975
32.9 34.2 35.5 36.8 38.1 39.4 40.6 41.9 43.2 44.5 45.7 47.0 59.3 71.4 83.3 95.0
106.6 118.1 129.6
iciency is the
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s a lower limnd the appro
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R SETUP ION
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10.311.011.712.413.113.814.615.316.016.824.432.440.548.857.265.674.2
e percentage
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Issue DatAugust 20Revision
rements
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91 9
00 7 4
6
0
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2 6 2
e of radiation
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RP 5
1 Page 4
n detected of
ming the
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5.0
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3
3.6.2
3.6.3
.7 Daily Ope
3.7.1
3.7.2
3.7.3
.8 Smear Co
3.8.1
3.8.2
3.8.3
3.8.4
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ollection
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SMEAR CAND
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he MDA forount times.
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nd count ratend count tim
ount time (m
calculate the
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R SETUP ION
∗ ∗
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Issue DatAugust 20Revision
the appropria
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ch of the proj
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te 013
RP 5
1 Page 5
ate project
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5.0
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3.9 Smear Co
3.9.1
3.9.2
3.9.3
3.9.4
3.9.5
3.9.6
3.9.7
3.9.8
3.8.4.1 Iss
3.8.4.2 U
3.8.4.3 Pfbp
ounting.
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NOTE: T
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Unlock the
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3.9.7.1 Ecb
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SMEAR CAND
f the item orsurvey the lasurvey sheet.
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COUNTERD OPERATI
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R SETUP ION
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Issue DatAugust 20Revision
less than 100record that a
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ollection pap
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correct coluount time an
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RP 5
1 Page 6
0 cm2, then area on the
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References
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Proceduree are examplprocedure is eed to be uses needed, fordifferent pro
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rd 52 Radiat
R SETUP ION
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Issue DatAugust 20Revision
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1 Page 7
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5.0
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B
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1
2
3
4
5
6
7
8
9
10
11
12
13
14
15
16
17
18
19
20
Sum
Count
Average
Sum of squares
Chi square value
ackground 9
pha Beta Alp
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e
Tc‐99
240 dpm 201
pha Beta Alp
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SMEAR CO
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OUNTER SETOPERATION
ter Setup Form
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beta
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m
Chi
Alpha
t (xi‐t)2
Issue DaAugust 2Revision
Instrument Id
Model
SN
Counter
SN
Cal due date
Source ID
Serial #
Half‐life Yrs
Assay Date
Activity dpm
ate 013
R
n 1 Pag
Check Sources
Beta
Tc‐99
99TC2203927
211000
12/14/1999
9240
RP 5.0
ge 8 of 12
Alpha
Th‐230
11438
75380
11/24/1981
20100
N‐1
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10 Bkg
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TUP AND Issue DaAugust 2Revision
ate 013
R
n 1 Pag
RP 5.0
ge 9 of 12
Initial QC Set Up
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1 02 03 04 05 06 07 08 09 010 0
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R
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RP 5.0
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Date
Initials
B
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Issue DaAugust 2Revision
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2 min bkdg
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D Issue DaSeptemb
2012 Revision
ments are loc
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ncy; assume
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n 0 Page 3
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3.4.1
DocumentsAny forms innformation nncluded in thhown in the dditional app
.1 Samp
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.3 Packa
References
.1 URS S
Contamin
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If all meas
s Generatencluded in thnecessary to his procedureexample is iplicable info
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Table 1
lpha emitters
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Proceduree are examplprocedure is eed to be uses needed, fordifferent pro
esults.
ndard 52 Ra
ING, ANDSTODY
Max
Non-(dpm/
s 22
2
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e les that showappropriateled as long asrms may be mojects.
adiation Prot
D Issue DaSeptemb
2012 Revision
imum Perm
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20
22
its, release th
w the minimuly followed. s all of the inmodified to
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n 0 Page 4
missible Lim
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40,000
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6.0
4 of 4
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cm2)
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