United States Air and EPA 520/1 -89-002
Environmental Protection Radiation (6602J) October 1989
Agency
vvEPA A Guide For Determining
Compliance With The
Clean Air Act Standards
For Radionuclide Emissions
From NRC-Licensed And
Non-DOE Federal
Revision 2
Recycled/Recyclable
Printed with Soy/Canola Ink on paper that
contains al least 50% recycled fiber
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Dear NRC Licensee:
A Federal Register notice was published January 28, 1994,
(59 FR 4228), confirming that 40 CFR part 61, subpart I, National
Emissions Standards for Radionuclide Emissions from Facilities
Licensed by the Nuclear Regulatory Commission and Federal
Facilities Not Operated by the Department of Energy/ is presently
in effect for two categories: (1) facilities licensed by the
Nuclear Regulatory Commission (NRC) or NRC Agreement States
except for commercial nuclear power reactors and (2) all federal
facilities not operated by the Department of Energy (DOE).
Facilities that handle only sealed sources are exempt. The
effectiveness of Subpart I is presently stayed for commercial
nuclear power reactors. The previous stay of Subpart I for NRC
and Agreement State licensees other than nuclear power reactors
expired on November 15, 1992, and has not been extended or
renewed. Further information, including a copy of the rule, is
being sent to you through NRC newsletters.
Those facilities which are not exempt from reporting
requirements must submit an annual report concerning emissions
for calendar year 1993 to EPA by March 31, 1994. Facilities that
are subject to reporting requirements but are unable to gather
the necessary information and report to EPA by March 31, 1994
should request an extension from the appropriate EPA regional
office. EPA will consider extensions of up to 60 days.
In order to assist licensees in determining compliance with
Subpart I, EPA used mailing labels supplied by NRC to send copies
of a guide for determining compliance to NRC licensees.
Unfortunately, during printing the covers of two documents were
switched, and some of you may have received a copy of the "User's
Guide for the Comply Code" (EPA 5201-89-003) with a cover that
reads "A Guide for Determining Compliance with the Clean Act
Standards for Radionuclide Emissions from NRC-Licensed and non-
DOE Federal Facilities." The correct guide for determining
compliance is attached. You may wish to remove the cover from
the other document and retain the "User's Guide" for future use.
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EPA 520/1-89-002
A GUIDE FOR DETERMINING COMPLIANCE WITH THE
CLEAN AIR ACT STANDARDS FOR RADIONUCLIDE EMISSIONS
FROM NEC-LICENSED AND NON-DOE FEDERAL FACILITIES
(Revision 2)
U.S. ENVIRONMENTAL PROTECTION AGENCY
Office of Radiation and Indoor Air
401 M Street, S.W.
Washington, DC 20460
October 1989
Printed on Recycled Paper
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TABLE OF CONTENTS
Page
1. INTRODUCTION 1-1
1.1 Applicability 1-1
1.2 Background and Purpose 1-1
1.3 How to Use This Guidance Document 1-3
2. DETERMINING EXEMPTION AND DEMONSTRATING COMPLIANCE 2-1
2.1 Introduction 2-1
2.2 Choosing a Procedure 2-1
3. WORKSHEETS 3-1
Worksheet A - NESHAPS Applicability 3-2
Worksheet B - Possession Table 3-4
Worksheet C - Concentration Table 3-21
Worksheet D - Stack or Vent Characteristics 3-31
Worksheet E - Release Rates 3-35
Worksheet F - NCRP Commentary No. 3 3-43
4. REPORTING AND RECORDKEEPING REQUIREMENTS 4-1
4.1 Reporting Requirements 4-1
4.2 Recordkeeping Requirements 4-4
5. RESOLVING PROBLEMS AND CONTACTING THE EPA 5-1
5.1 EPA Contacts 5-1
5.2 Sources 5-1
REFERENCES
111
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LIST OF FIGURES
Page
3-1. Distance Between Source and
Nearest Receptor or Farm 3-45
3-2. Definition of Release Heights 3-46
5-1. EPA Regional Offices 5-2
LIST OF TABLES
2-1. Input Parameters Required for
Various Methods 2-6
3-1. Annual Possession Quantities for
Environmental Compliance 3-9
3-2. Concentration Levels for Environmental
Compliance 3-25
3-3. Adjustments to Emission Factors
for Effluent Controls 3-41
5-1. EPA Regional Program Managers 5-3
IV
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1. INTRODUCTION
1.1 APPLICABILITY
The requirements described in this document apply to certain
facilities licensed by the Nuclear Regulatory Commission (NRC)
or its Agreement States to handle radioactive materials.
Federal facilities not part of the Department of Energy (DOE)
are also covered.
You may not be subject to these requirements. If you are
uncertain, fill out Worksheet A in Section 3 to determine
whether the requirements apply. If you are not subject to the
requirements, you need read no further.
1.2 BACKGROUND AND PURPOSE
On February 6, 1985, the Environmental Protection Agency (EPA)
issued standards under Section 112 of the Clean Air Act that
limit airborne emissions of radionuclides to the atmosphere.
In February 1989 these standards were re-proposed, and in
November 1989 final standards may be promulgated. This
document provides guidance for determining compliance with one
of the National Emission Standards for Hazardous Air
Pollutants (NESHAPS) covering facilities that are licensed by
the NRC, and Federal facilities not operated by the DOE, that
could emit radionuclides to the air. See the Code of Federal
Regulations, Title 40, Part 61, Subpart I (40 CFR 61,
Subpart I).
1-1
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Facilities covered by Subpart I should use this document.
They include all Federal facilities that emit radionuclides to
the air (except those owned or operated by the DOE), and all
facilities licensed by the NRC or its Agreement States. The
proposed standard does not apply to disposal at facilities
under 40 CFR Parts 191 subpart B*, to facilities that use only
sealed radiation sources, or to low energy accelerators.
Examples of the types of facilities covered include
radiopharmaceutical suppliers and users, shipyards, research
facilities, test and research reactors, radiation source
manufacturers, and power reactors under the uranium fuel
cycle.
The standard requires that existing facilities file an annual
report with the EPA. It also requires that an application to
construct or modify be filed with the EPA for new facilities
or proposed modifications to existing facilities. In most
cases, you will be exempt from reporting or filing an
application with the EPA if your facility's emissions lead to
calculated doses that are a factor of ten lower than the
standard.
The EPA has developed methods for you to use to determine
whether your facility is in compliance with 40 CFR Part 61,
Subpart I, and whether it is exempt from reporting. The
overall approach is a tiered set of methods intended to
minimize the burden on those facilities covered by the
standard. This approach begins with simple-to-use methods
that are very conservative in terms of determining compliance.
The methods become progressively less conservative but more
complicated at succeeding levels.
* Part 191 deals with high-level and transuranic waste and
spent fuel.
1-2
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If you cannot demonstrate compliance with the standard by
using any of the methods described in Section 3, you should
contact the EPA Program Managers at your regional EPA office.
(See Section 5.)
1.3 HOW TO USE THIS GUIDANCE DOCUMENT
The remainder of this document gives the details of this
tiered approach. Each method is keyed to a worksheet. These
worksheets explain the purpose of the relevant step and list
useful references. They also list the data you will need and
provide a step-by-step procedure for determining whether your
facility is in compliance with the standard and whether you
need to report to the EPA. Section 2 briefly describes each
method and the assump-
tions on which it is based. The worksheets are in Section 3.
Section 4 contains a summary of reporting and recordkeeping
requirements, and Section 5 discusses when and how to contact
the EPA to resolve any problems or issues specific to your
facility.
1-3
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2. DETERMINING EXEMPTION AND DEMONSTRATING COMPLIANCE
2.1 INTRODUCTION
This section outlines the methods used to determine if you are
covered by the standard, if you comply with the requirements,
or if you are exempt from reporting.
Begin by completing Worksheet A to see whether you are subject
to the requirements. If you are exempt from the requirements,
you need go no further.
To determine whether you comply with the standard and are
exempt from reporting, or whether you comply but must report,
you must estimate the radiation dose to the nearest receptor
(resident, home, school, business, or office) as a result of
airborne emissions of radioactivity from your facility. This
section describes the methods approved by the EPA for making
such dose estimates. There are several approaches because of
the diversity of facilities regulated under the standard. The
simplest methods do not estimate the radiation dose directly.
Instead, they determine whether your emissions could not cause
a dose greater than the standard.
2.2 CHOOSING A PROCEDURE
This section describes four alternative procedures for
determining compliance with the standard. A very brief
description of all the methods and the assumptions on which
they are based follows. However, you should first check Table
3-1 or 3-2 to see if the radionuclides that
2-1
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you are using are handled by COMPLY. If they are not, contact
your EPA Regional Program Manager listed in
Table 5-1.
Possession Table - Procedure #1
The Possession Table allows you to determine compliance from
the amount of radionuclides used annually at your facility.
You should use this method if you handle only small quantities
and you do not have measured stack concentrations. The annual
quantities were calculated using assumptions that tend to
overestimate the dose. This procedure may be used to
determine exemption from reporting and to demonstrate
compliance. See the instructions for Worksheet B for the
restrictions on using this method.
Concentration Table - Procedure #2
You should use this approach if you have measured stack
concentrations or have EPA approval to measure air
concentrations at the receptor. The approach is generally
based on the concentration of radionuclides in the emissions.
For each radionuclide, the concentration limit ensures that a
person exposed to that concentration for a full year would not
receive a dose that exceeds the standard. This method assumes
no dispersion from the point of release to where the most
exposed person lives and assumes that all of the person's food
is grown at his home. This procedure may be used to determine
exemption from reporting and to demonstrate compliance. See
the instructions for Worksheet C for the restrictions on using
this method.
2-2
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Screening Model - Procedure #3
This method consists of three screening levels. You should
use this approach if you cannot satisfy the requirements using
the possession or concentration tables. This method requires
that you develop a small amount of site-specific data
(quantities of nuclides released, the facility's physical
configuration, and distance to the nearest person from the
point of release). Detailed radionuclide, meteorological, and
demographic information is not needed because the dose factors
and dispersion models incorporate assumptions that tend to
overestimate the dose. This method may be used to determine
exemption from reporting or filing and to demonstrate
compliance. At present, NCRP Commentary No. 3 provides
procedures for calculating organ doses as well as effective
whole body dose equivalents. Organ doses are not required to
demonstrate compliance.
You may either do the calculations by hand or use the COMPLY
computer code. If you use the Screening Model, you will need
to fill out Worksheets D and E and obtain either the User's
Guide for the COMPLY code or National Council on Radiation
Protection and Measurements (NCRP) Commentary No. 3. (See
Section 5 for information on how to obtain these documents and
the code.) Table 2-1 lists the parameters you will need to do
the calculations in NCRP Commentary No. 3, and for input into
the COMPLY code. If you use NCRP Commentary No. 3, or the
COMPLY code, you will also need to fill out Worksheet F.
2-3
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Compliance Model - Procedure #4
The Compliance Model is an extension of the NCRP Screening
Levels but produces a more accurate dose estimate by providing
for more complete treatment of air dispersion, and a separate
location for the production of each type of food. In
addition, the pathway parameters are less conservative. This
greater precision requires some additional site-specific data.
This method is the highest level in the COMPLY computer code.
If you use this method, you will need to fill out Worksheets
D and E and obtain the COMPLY code and its user's guide. (See
Section 5 for information on how to obtain these.) You will
also need to fill out Worksheet F.
Table 2-1 is a list of the parameters you need at various
levels for the NCRP Screening Levels and the COMPLY code. Not
all parameters are needed at all levels; the need is
determined by the particular configuration of your facility.
The footnotes to Table 2-1 briefly describe when a particular
parameter is needed. A precise definition of each of these
parameters is given in the User's Guide for the COMPLY Code.
Use of the COMPLY Code
The first three procedures can be done either by hand
following the steps of NCRP Commentary No. 3, or by means of
the COMPLY computer code. See Worksheet F. It is not
practical to do by hand the complicated calculations in
Procedure #4 which is contained in the COMPLY code. However,
only facilities that handle and release radionuclides having
the potential to cause doses greater than 10% of the standard
will need to use this method.
2-4
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The COMPLY code runs on an IBM PC or PC-compatible computer
and has been designed for users with limited computer
experience. The program will ask you for the information it
needs and will produce most of the report for you. You must
decide initially which of the methods to use, but the program
does all the numerical calculations. Thus, if your initial
choice of method is inappropriate, you have lost only a few
minutes of time, not several hours.
If your facility handles more than about six nuclides or has
multiple release points (stacks or vents), we recommend using
the COMPLY code. Doing the calculations for multiple nuclides
or release points by hand can become very difficult.
The initial choice of one method does not preclude you from
using another method, provided that you have the necessary
information and you meet the restrictions associated with that
method.
2-5
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Table 2-1. Input parameters required for various methods
Parameter
Nuclide names
Stack concentrations
Annual possession amounts
Release rates
Release height
Building height
Stack or vent diameter*
Volumetric flow rateA
Distance from source to
receptor
Building width8
Wind speed0
Distances to sources of
food production (farms)0
Stack temperatureE
Ambient air temperatureE
Wind roseF
Building length0
NCRP
Level
1-3
N/A
N/A
1-3
2-3
2-3
2-3
1-3
2-3
2-3
2-3
2-3
N/A
N/A
N/A
N/A
COMPLY
Level
1-4
1
1
2-4
2-4
2-4
2-4
2-4
2-4
2-4
2-4
Default
Value
None
None
None
None
None
None
None
0.3 m3/s
None
None
2 m/s
3-4
4
4
4
4
None
55°F
55°F
None
None
Notes:
A. Needed at levels 2 and 3 only if source and receptor are on the
same building. Needed at level 4 if source and receptor are on
the same building or if stack height is more than 2.5 times
building height.
B. Needed only if stack height is less than or equal to 2.5 times
building height.
C. At level 4, needed only if user has not specified a wind rose.
D. At level 3, there are two farms—one for vegetables and one for
milk and meat. At level 4, there are three farms—one each for
vegetables, milk, and meat.
E. Needed if stack height is more than 2.5 times building height.
F. Optional.
G. Needed only if stack height is less than or equal to 2.5 times the
building height and the user has specified a wind rose.
2-6
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WORKSHEETS
The following worksheets provide a step-by-step approach to each method
described in Section 2. Each worksheet on the following pages contains
a list of the parameters needed to complete the worksheet and
line-by-line instructions.
Note: If you use the COMPLY code, you need not fill out Worksheets B
and C.
The worksheets shown here have space for only three nuclides. If your
facility handles more than three, we suggest you make your own
worksheets using these as guides. On each page, be sure to identify the
worksheet number, your facility name, and the assessment period (one
calendar year for existing facilities, and a one-year period for
facilities not yet constructed), and use the same line numbers as those
on the worksheets given here.
3-1
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WORKSHEET A - NESHAPS Applicability
INTRODUCTION
Sections 61.100 and 61.101 of 40 CFR Part 61, Subpart I, define the
facilities covered by this standard. The questions on Worksheet A
provide a step-by-step procedure to determine whether your facility is
covered. The standard applies to existing facilities, modifications to
existing facilities, and new or proposed facilities. Check the proper
"yes" or "no" space for each question and follow the related
instruction.
EXPLANATION OF WORKSHEET A ITEMS
1. Self-explanatory.
2. Facilities owned or operated by an agency of the Federal Government
(other than the Department of Energy) include those operated by
contractors to those agencies.
3. Part 191 deals with high-level and transuranic waste and spent fuel.
4. Only unsealed sources are covered under this rule, and a source is
considered to be sealed unless opened. "Special Form" sources are
exempt as are any sealed sources that are sealed and not intended to be
opened in their routine application (e.g., thickness gauges).
5. Self-explanatory.
3-2
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WORKSHEET A - NESHAPS Applicability
Facility Name:
Assessment Period (dates):
Does your facility have a license issued by the NRC or any
Agreement State to receive title to, receive, possess, use,
transfer, or deliver any source, byproduct, or special nuclear
material?
Yes : Go to Step 3
No : Go to Step 2
Is your facility owned or operated by an agency of the Federal
Government other than the Department of Energy?
Yes _ : Go to Step 3
No : Stop. You are not covered by this
subpart I of this rule.
Is your facility engaged in disposal under 40 CFR Part 191 subpart
B or do you operate only a low-energy accelerator?
Yes : Stop. You are not covered by this
rule.
No : Go to Step 4
Does your facility handle sealed radiation sources exclusively?
Yes : Stop. You are not covered by this
rule.
No : This rule does apply to your
facility. Go to Step 5.
You are subject to EPA's radionuclide air emission standard.
Section 2 of this document explains how to determine exemption from
reporting, and how to demonstrate compliance with the standard.
3-3
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WORKSHEET B - POSSESSION TABLE
INTRODUCTION
The Possession Table provides a simple method for determining if you are
in compliance with the standard and exempt from reporting. You may use
the Possession Table only if your facility meets both of the following
conditions:
1. There is no receptor within 10 meters" of any release point; and
2. No milk, meat, or vegetables are produced within 100 meters* of any
release point.
If you do not meet both of these conditions, use another method (see
Section 2.2). If you do meet these conditions and wish to use the
Possession Table, you will need the following information:
1. A list of all radionuclides used in your facility during the
reporting period.
2. The amount (in curies) of each radionuclide you had on hand at the
beginning of the reporting period.
This is the straight-line distance determined from a plan
view. See Figure 3-1 at the end of this Section.
3-4
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3. The amount (in curies) of each radionuclide that you received at
your facility during the reporting period.
4. The physical form (gas, liquid or powder, or solid") of each
radionuclide and the maximum temperature to which it is exposed in
your facility.
Given this information, use Worksheet B to determine if you are in
compliance or exempt from reporting. Or, you may use the computer
program COMPLY. See the User's Guide for the COMPLY Code (EPA89a).
EXPLANATION OF WORKSHEET B ITEMS
1. If a nuclide is in more than one physical form (gas, liquid or
powder, or solid), enter its name once for each form. See item 5
below for restrictions on these forms.
2. This is the amount of each nuclide (in curies) contained in
inventory at the beginning of the assessment period. Any material
in sealed containers that were not opened during the assessment
period, and did not leak, should not be included.
3. This is the amount of each nuclide (in curies) received at the
facility during the assessment period. Any material in sealed
containers that were not opened throughout the assessment period,
and did not leak, should not be included.
"Capsules containing radionuclides in liquid or powder
form can be considered to be solids.
3-5
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4. Self-explanatory.
5. This must be a gas, a liquid or powder, or a solid. If any nuclide
is exposed to a temperature of 100 degrees Celsius or more, or
boils at a temperature of 100 degrees Celsius or less, it must be
considered to be a gas. Any nuclide that is intentionally
dispersed into the environment must be considered to be a gas; for
example, radioactive tracers that are released into wells or rivers
to determine ground water flow.
6. Table 3-1 lists the annual possession quantity for each nuclide by
name and by physical form. Find the nuclide name and enter the
number given in the column corresponding to its physical form on
line 5. If you use radionuclides that are not on this list,
contact the EPA.
7. This is the ratio of your amount to the annual possession quantity.
8. This is the sum of all the ratios on line 7-
9. This is the sum of the ratios from line 7 for radioiodines.
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WORKSHEET B - POSSESSION TABLE
Facility Name:
Assessment Period (dates):
1. Enter the name of
each nuclide (i.e.,
1-131, Co-60, etc.).
If a nuclide is in
more than one physi-
cal form, enter its
name once for each
physical form.
2. Enter the curies
on hand at the
beginning of the
period.
3. Enter the curies
produced or received _
during the period.
4. Add lines 2 and 3. _
5. Enter the physical
form of the nuclide- _
gas, liquid or powder,
or solid or capsule
(G, L, or S). If any
nuclide is exposed
to temperatures of
100 °C or more, or boils
at 100 °C or less,
treat it as a gas.
6. Enter the value
shown in Table 3-1 _
for the appropriate
form of each nuclide.
7. Divide line 4 by
line 6. _
8. Sum the fractions
on line 7.
9. Sum the fractions
on line 7 due to
radioiodines.
3-7
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WORKSHEET B (page 2 of 2)
If the value on line 8 is less than 0.1 and the value on line 9 is less
than 0.03 and both represent the dose caused by the entire facility with
any new construction or modification, you are exempt from reporting or
submitting an application to construct or modify. If the value on line
8 is less than 0.01 and the value on line 9 is less than 0.003 and both
represent the dose caused only by any new construction or modification,
you are exempt from applying for an application to construct or modify
that would otherwise be required under 40 CFR 61, Subpart I. Retain
this worksheet for possible review by the EPA.
If the value on line 8 is equal to or greater than 0.1 but less than or
equal to 1.0, and the value on line 9 is equal to or greater than 0.03
but less than or equal to 0.3, you are in compliance but are not exempt
from reporting to the EPA. If the value on line 8 is equal to or
greater than 0.01 and the value on line 9 is equal to or greater than
0.003 and both represent the dose caused only by any new construction or
modification, you are not exempt from reporting to the EPA. You may, if
you like, use a different method to determine if you are exempt. Retain
this worksheet for possible use later.
If the value on line 8 is greater than 1.0, or the value on line 9 is
greater than 0.3, you have not demonstrated compliance. You should use
another method to determine if you can meet the standard.
3-8
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Table 3-1
Annual Possession Quantities for Environmental
Compliance
Radionuclide
Annual Possession Quantities (Ci/yr)
Liquid/
Gaseous Powder Solid
Form" Forms Form*
Ac-225
Ac-227
Ac-228
Ag-106
Ag-106m
Ag-108m
Ag-llOm
Ag-111
Al-26
Am-241
Am-242
Am-242m
Am-243
Am-244
Am-245
Am-246
Ar-37
Ar-41
As-72
As-73
As-74
As-76
As-77
At-211
Au-193
Au-194
Au-195
Au-198
Au-199
Ba-131
Ba-133
Ba-133m
Ba-135m
Ba-139
Ba-140
9.6E-05
1.6E-07
3.4E-03
1.6E+00
2.6E-03
6.5E-06
9.4E-05
6.7E-02
4.0E-06
2.3E-06
1.8E-02
2.5E-06
2.3E-06
4.6E-02
7.0E+00
9.8E-01
1.4E+06
1.4E+00
2.9E-02
6.0E-02
4.3E-03
8.8E-02
7.9E-01
l.OE-02
4.2E-01
3.5E-02
3.3E-03
4.6E-02
1.5E-01
l.OE-02
4.9E-05
9.3E-02
5.8E-01
4.7E+00
2.1E-03
9.6E-02
1.6E-04
3.4E+00
1.6E+03
2.6E+00
6.5E-03
9.4E-02
6.7E+01
4.0E-03
2.3E-03
1.8E+01
2.5E-03
2.3E-03
4.6E+01
7.0E+03
9.8E+02
-
-
2.9E+01
6.0E+01
4.3E+00
8.8E+01
7.9E+02
l.OE+01
4.2E+02
3.5E+01
3.3E+00
4.6E+01
1.5E+02
l.OE+01
4.9E-02
9.3E+01
5.8E+02
4.7E+03
2.1E-I-00
9.6E+01
1.6E-01
3.4E+03
1.6E+06
2.6E+03
6.5E+00
9.4E+01
6.7E+04
4.0E+00
2.3E+00
1.8E+04
2.5E+00
2.3E+00
4.6E+04
7.0E+06
9.8E+05
-
-
2.9E+04
6.0E+04
4.3E+03
8.8E+04
7.9E+05
l.OE+04
4.2E+05
3.5E+04
3.3E+03
4.6E+04
1.5E+05
l.OE+04
4.9E+01
9.3E+04
5.8E+05
4.7E+06
2.1E+03
See footnotes at the end of the table,
3-9
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Table 3-1
Radionuclide
Annual Possession Quantities for Environmental
Compliance (continued)
Annual Possession Quantities (Ci/yr)
Liquid/
Gaseous Powder Solid
Form* Forms Form*
Ba-141
Ba-142
Be-7
Be-10
Bi-206
Bi-207
Bi-210
Bi-212
Bi-213
Bi-214
Bk-249
Bk-250
Br-77
Br-80
Br-80m
Br-82
Br-83
Br-84
C-ll
C-14
Ca-41
Ca-45
Ca-47
Cd-109
Cd-113
Cd-113m
Cd-115
Cd-115m
Cd-117
Cd-117m
Ce-139
Ce-141
Ce-143
Ce-144
Cf-248
1.3E+00
1.1E+00
2.3E-02
3.0E-03
3.1E-03
8.4E-06
4.2E-03
4.7E-02
6.0E-02
1.4E-01
7.0E-04
l.OE-01
7.5E-02
1.2E+01
1.5E+00
1.6E-02
9.9E+00
5.6E-01
1.3E+00
2.9E-01
2.7E-02
5.8E-02
1.1E-02
5.0E-03
3.3E-04
4.4E-04
5.4E-02
l.OE-02
5.6E-02
1.3E-01
2.6E-03
1.8E-02
l.OE-01
1.7E-03
2.0E-05
1.3E+03
l.lE-t-03
2.3E+01
3.0E+00
3.1E+00
8.4E-03
4.2E+00
4.7E+01
6.0E+01
1.4E+02
7.0E-01
l.OE+02
7.5E+01
1.2E+04
1.5E+03
1.6E+01
9.9E+03
5.6E+02
1.3E+03
2.9E+02
2.7E+01
5.8E+01
1.1E+01
5.0E+00
3.3E-01
4.4E-01
5.4E+01
l.OE+01
5.6E+01
1.3E+02
2.6E+00
1.8E+01
l.OE+02
1.7E+00
2.0E-02
1.3E+06
1.1E+06
2.3E+04
3.0E+03
3.1E+03
8.4E+00
4.2E+03
4.7E+04
6.0E+04
1.4E+05
7.0E+02
l.OE+05
7.5E+04
1.2E+07
1.5E+06
1.6E+04
9.9E+06
5.6E+05
1.3E+06
2.9E+05
2.7E+04
5.8E+04
1.1E+04
5.0E+03
3.3E+02
4.4E+02
5.4E+04
l.OE+04
5.6E+04
1.3E+05
2.6E+03
1.8E+04
l.OE+05
1.7E+03
2.0E+01
See footnotes at the end of the table.
3-10
-------
Table 3-1
Annual Possession Quantities for Environmental.
Compliance (continued)
Radionuclide
Annual Possession Quantities (Ci/yr)
Liquid/
Gaseous Powder Solid
Form* Forms Form*
Cf-249
Cf-250
Cf-251
Cf-252
Cf-253
Cf-254
Cl-36
Cl-38
Cm-242
Cm-243
Cm-244
Cm-245
Cm-246
Cm-247
Cm-248
Cm-249
Cm-250
Co-56
Co-57
Co-58
Co-58m
Co- 60
Co-60m
Co-61
Cr-49
Cr-51
Cs-129
Cs-131
Cs-132
Cs-134
Cs-134m
Cs-135
Cs-136
CS-137
Cs-138
1.7E-06
4.0E-06
1.7E-06
6.4E-06
3.3E-04
3.6E-06
1.9E-04
6.5E-Q1
6.0E-05
3.3E-06
4.2E-06
2.3E-06
2.3E-06
2.3E-06
6.4E-07
4.6E+00
1.1E-07
2.4E-04
1.6E-03
9.0E-04
1.7E-01
1.6E-05
4.0E+00
3.8E+00
9.0E-01
6.3E-02
1.5E-01
2.8E-01
1.3E-02
5.2E-05
3.2E-01
2.4E-02
2.1E-03
2.3E-05
4.4E-01
1.7E-03
4.0E-03
1.7E-03
6.4E-03
3.3E-01
3.6E-03
1.9E-01
6.5E+02
6.0E-02
3.3E-03
4.2E-03
2.3E-03
2.3E-03
2.3E-03
6.4E-04
4.6E+03
1.1E-04
2.4E-01
1.6E+00
9.0E-01
1.7E+02
1.6E-02
4.0E+03
3.8E+03
9.0E+02
6.3E+01
1.5E+02
2.8E+02
1.3E+01
5.2E-02
3.2E+02
2.4E+01
2.1E+00
2.3E-02
4.4E+02
1.7E+00
4.0E+00
1-.7E+00
6.4E+00
3.3E+02
3.6E+00
1.9E+02
6.5E+05
6.0E+01
3.3E+00
4.2E+00
2.3E+00
2.3E+00
2.3E+00
6.4E-01
4.6E+06
1.1E-01
2.4E+02
1.6E+03
9.0E+02
1.7E+05
1.6E+01
4.0E+06
3.8E+06
9.0E+05
6.3E+04
1.5E+05
2.8E+05
1.3E+04
5.2E+01
3.2E+05
2.4E+04
2.1E+03
2.3E+01
4.4E+05
See footnotes at the end of the table.
3-11
-------
Table 3-1
Radionuclide
Annual Possession Quantities for Environmental
Compliance (continued)
Annual Possession Quantities (Ci/yr)
Liquid/
Gaseous Powder Solid
Form* Forms Form*
Cu-61
Cu-64
CU-67
Dy-157
Dy-165
Dy-166
Er-169
Er-171
Es-253
Es-254
Es-254m
Eu-152
Eu-152m
Eu-154
Eu-155
Eu-156
F-18
Fe-52
Fe-55
Fe-59
Fm-254
Fm-255
Fr-223
Ga-66
Ga-67
Ga-68
Ga-72
Gd-152
Gd-153
Gd-159
Ge-68
Ge-71
Ge-77
H-3
Hf-181
4.0E-01
5.2E-01
1.5E-01
4.4E-01
5.6E+00
8.1E-02
4.0E-01
3.6E-01
2.6E-04
2.3E-05
1.8E-03
1.6E-05
3.5E-01
2.0E-05
5.2E-04
3.2E-03
5.6E-01
4.9E-02
1.4E-01
1.3E-03
1.8E-02
4.0E-03
1.4E-01
5.6E-02
1.1E-01
7.6E-01
3.6E-02
4.4E-06
2.0E-03
6.8E-01
2.3E-04
2.6E+00
l.OE-01
1.5E+01
2.5E-03
4.0E+02
5.2E+02
1.5E+02
4.4E+02
5.6E+03
8.1E+01
4.0E+02
3.6E+02
2.6E-01
2.3E-02
1.8E+00
1.6E-02
3.5E+02
2.0E-02
5.2E-01
3.2E+00
5.6E+02
4.9E+01
1.4E+02
1.3E+00
1.8E+01
4.0E+00
1.4E+02
5.6E+01
1.1E+02
7.6E+02
3.6E+01
4.4E-03
2.0E+00
6.8E+02
2.3E-01
2.6E+03
l.OE+02
1.5E+04
2.5E+00
4.0E+05
5.2E+05
1.5E+05
4.4E+05
5.6E+06
8.1E+04
4.0E+05
3 . 6E+05
2.6E+02
2.3E+01
1.8E+03
1.6E+01
3 . 5E+05
2.0E+01
5.2E+02
3.2E+03
5.6E+05
4.9E+04
1.4E+05
1.3E+03
1.8E+04
4.0E+03
1.4E+05
5.6E+04
1.1E+05
7.6E+05
3.6E+04
4.4E+00
2.0E+03
6.8E+05
2.3E+02
2.6E+06
l.OE+05
1.5E+07
2.5E+03
See footnotes at the end of the table.
3-12
-------
Table 3-1
Annual Possession Quantities for Environmental
Compliance (continued)
Radionuclide
Annual Possession Quantities (Ci/yr)
Liquid/
Gaseous Powder Solid
Form* Forms Form*
Hg-193m
Hg-197
Hg-197m
Hg-203
Ho-166
Ho-166m
1-123
1-124
1-125
1-126
1-128
1-129
1-130
1-131
1-132
1-133
1-134
1-135
In-Ill
In-113m
In-114m
In-115
In-115m
In-116m
In-117
»
In-117m
Ir-190
Ir-192
Ir-194
Ir-194m
K-40
K-42
K-43
K-44
Kr-79
9.5E-02
2.4E-01
2.5E-01
5.2E-03
2.8E-01
6.0E-06
4.9E-01
9.3E-03
6.2E-03
3.7E-03
9.3E+00
2.6E-04
4.6E-02
6.7E-03
2.0E-01
6.7E-02
3.2E-01
1.2E-01
4.9E-02
2.1E+00
4.9E-03
2.7E-04
1.4E+00
3.5E-01
1.3E+00
7.6E-02
3.5E-03
9.7E-04
2.5E-01
1.5E-04
6.8E-05
2.9E-01
6.0E-02
4.9E-01
7.0E+00
9.5E+01
2.4E+02
2.5E+02
5.2E+00
2.8E+02
6.0E-03
4.9E+02
9.3E+00
6.2E+00
3.7E+00
9.3E+03
2.6E-01
4.6E+Q1
6.7E+00
2.0E+02
6.7E+01
3.2E+02
1.2E+02
4.9E+01
2.1E+03
4.9E+00
2.7E-01
1.4E+03
3.5E+02
1.3E+03
7.6E+01
3.5E+00
9.7E-01
2.5E+02
1.5E-01
6.8E-02
2.9E+02
6.0E+01
4.9E+02
-
9.5E+04
2.4E+05
2.5E+05
5.2E+03
2.8E+05
6.0E+00
4.9E+05
9.3E+03
6.2E+03
3.7E+03
9.3E+06
2.6E+02
4.6E+04
6.7E+03
2.0E+05
6.7E+04
3.2E+05
1.2E+05
4.9E+04
2.1E+06
4.9E+03
2.7E+02
1.4E+06
3.5E+05
1.3E+06
7.6E+04
3.5E+03
9.7E+02
2.5E+05
1.5E+02
6.8E+01
2.9E+05
6.0E+04
4.9E+05
-
See footnotes at the end of the table
3-13
-------
Table 3-1
Radionuclide
Annual Possession Quantities for Environmental,
Compliance Ccontinued)
Annual Possession Quantities (Ci/yr)
Liquid/
Gaseous Powder Solid
Form* Forms Form*
Kr-81
Kr-83m
Kr-85
Kr-85m
Kr-87
Kr-88
La-140
La-141
La-142
Lu-177
Lu-177m
Mg-28
Mn-52
Mn-52m
Mn-53
Mn-54
Mn-56
Mo-93
Mo-99"
Mo-101
Na-22
Na-24
Nb-90
Nb-93m
Nb-94
Nb-95
Nb-95m
Nb-96
Nb-97
Nd-147
Nd-149
Ni-56
Ni-57
Ni-59
Ni-63
1.8E+02
2. OE+04
8.4E+02
1.1E+01
2.0E+00
4.2E-01
1.6E-02
1.1E+00
2.3E-01
1.4E-01
3.5E-04
2.1E-02
3.5E-03
5.2E-01
5.7E-02
2.5E-04
2.5E-01
1.5E-03
5.7E-02
8.4E-01
3.2E-05
2.6E-02
2.5E-02
1.2E-02
6.0E-06
2.3E-03
2.0E-02
2.5E-02
l.OE+00
3.0E-02
1.1E+00
2.0E-03
2.1E-02
2.2E-02
1.4E-01
-
-
-
-
—
_
1.6E+01
1.1E+03
2.3E+02
1.4E+02
3.5E-01
2.1E+01
3.5E+00
5.2E+02
5.7E+01
2.5E-01
2.5E+02
1.5E+00
5.7E+01
8.4E+02
3.2E-02
2.6E+01
2.5E+01
1.2E+01
6.0E-03
2.3E+00
2.0E+01
2.5E+01
l.OE+03
3.0E+01
1.1E+03
2.0E+00
2.1E+01
2.2E+01
1.4E+02
-
-
-
-
—
_
1.6E+04
1.1E+06
2.3E+05
1.4E+05
3.5E+02
2.1E+04
3.5E+03
5.2E+05
5.7E+04
2.5E+02
2.5E+05
1.5E+03
5.7E+04
8.4E+05
3.2E+01
2.6E+04
2.5E+04
1.2E+04
6.0E+00
2.3E+03
2 . OE+04
2.5E+04
l.OE+06
3. OE+04
1.1E+06
2.0E+03
2.1E+04
2.2E+04
1.4E+05
See footnotes at the end of the table,
3-14
-------
Table 3-1
Annual Possession Quantities for Environmental
Compliance (continued)
Radionuclide
Annual Possession Quantities (Ci/yr)
Liquid/
Gaseous Powder Solid
Form* Forms Form*
Ni-65
Np-235
Np-237
Np-238
Np-239
Np-240
Np-240m
Os-185
Os-191m
Os-191
Os-193
P-32
P-33
Pa-230
Pa-231
Pa-233
Pa-234
Pb-203
Pb-205
Pb-209
Pb-210
Pb-211
Pb-212
Pb-214
Pd-103
Pd-107
Pd-109
Pm-143
Pm-144
Pm-145
Pm-146
Pm-147
Pm-148
Pm-148m
Pm-149
7.0E-01
3.0E-02
1.8E-06
1.9E-02
l.OE-01
6.5E-01
4.7E+00
9.2E-04
9.0E-01
3.8E-02
2.9E-01
1.7E-02
1.2E-01
6.3E-04
8.3E-07
9.3E-03
9.3E-02
8.3E-02
1.2E-02
1.1E+01
5.5E-05
1.2E-01
6.0E-03
1.2E-01
2.1E-01
8.2E-02
9.4E-01
7.6E-04
1.1E-04
5.2E-04
4.4E-05
2.6E-02
1.7E-02
7.6E-04
2.8E-01
7.0E+02
3.0E+01
1.8E-03
1.9E+01
l.OE+02
6.5E+02
4.7E+03
9.2E-01
9.0E+02
3.8E+01
2.9E+02
1.7E+01
1.2E+02
6.3E-01
8.3E-04
9.3E+00
9.3E+01
8.3E+01
1.2E+01
1.1E+04
5.5E-02
1.2E+02
6.0E+00
1.2E+02
2.1E+02
8.2E+01
9.4E+02
7.6E-01
1.1E-01
5.2E-01
4.4E-02
2.6E+01
1.7E+01
7.6E-01
2.8E+02
7.0E+05
3.0E+04
1.8E+00
1.9E+04
l.OE+05
6.5E+05
4.7E+06
9.2E+02
9.0E+05
3.8E+04
2.9E+05
1.7E+04
1.2E+05
6.3E+02
8.3E-01
9.3E+03
9.3E+04
8.3E+04
1.2E+04
1.1E+07
5.5E+01
1.2E+05
6.0E+03
1.2E+05
2.1E+05
8.2E+04
9.4E+05
7.6E+02
1.1E+02
5.2E+02
4.4E+01
2 . 6E+04
1.7E+04
7.6E+02
2.8E+05
See footnotes at the end of the table.
3-15
-------
Table 3-1
Radionuclide
Annual Possession Quantities for Environmental
Compliance (continued)
Annual Possession Quantities (Ci/yr)
Liquid/
Gaseous Powder Solid
Form* Forms Form*
Pm-151
Po-210
Pr-142
Pr-143
Pr-144
Pt-191
Pt-193
Pt-193m
Pt-195m
Pt-197
Pt-197m
Pu-236
Pu-237
Pu-238
Pu-239
Pu-240
Pu-241
Pu-242
PU-243
Pu-244
Pu-245
Pu-246
Ra-223
Ra-224
Ra-225
Ra-226
Ra-228
Rb-81
Rb-83
Rb-84
Rb-86
Rb-87
Rb-88
Rb-89
Re-184
1.2E-01
9.3E-05
2.8E-01
l.OE-01
1.5E+01
6.4E-02
2.1E-02
4.8E-01
1.4E-01
1.1E+00
3.6E+00
7.0E-06
2.3E-02
2.7E-06
2.5E-06
2.5E-06
1.3E-04
2.5E-06
3.8E+00
2.4E-06
2.1E-01
4.8E-03
1.3E-04
3.2E-04
1.3E-04
5.5E-06
1.3E-05
4.2E-01
1.4E-03
2.0E-03
1.7E-02
l.OE-02
1.7E+00
6.4E-01
1.8E-03
1.2E+02
9.3E-02
2.8E+02
l.OE+02
1.5E+04
6.4E+01
2.1E+01
4.8E+02
1.4E+02
1.1E+03
3.6E+03
7.0E-03
2.3E+01
2.7E-03
2.5E-03
2.5E-03
1.3E-01
2.5E-03
3.8E+03
2.4E-03
2.1E+02
4.8E+00
1.3E-01
3.2E-01
1.3E-01
5.5E-03
1.3E-02
4.2E+02
1.4E+00
2.0E+00
1.7E+01
l.OE+01
1.7E+03
6.4E+02
1.8E+00
1.2E+05
9.3E+01
2.8E+05
l.OE+05
1.5E+07
6.4E+04
2.1E+04
4.8E+05
1.4E+05
1.1E+06
3.6E+06
7.0E+00
2.3E+04
2.7E+00
2.5E+00
2.5E+00
1.3E+02
2.5E+00
3.8E+06
2.4E+00
2.1E+05
4.8E+03
1.3E+02
3.2E+02
1.3E+02
5.5E+00
1.3E+01
4.2E+05
1.4E+03
2.0E+03
1.7E+04
l.OE+04
1.7E+06
6.4E+05
1.8E+03
See footnotes at the end of the table,
3-16
-------
Table 3-1
Annual Possession Quantities for Environmental
Compliance (continued)
Radionuclide
Annual Possession Quantities (Ci/yr)
Liquid/
Gaseous Powder Solid
Form* Forms Form*
Re- 18 4m
Re-186
Re-187
Re-188
Rh-103m
Rh-105
Ru-97
Ru-103
Ru-105
Ru-106
S-35
Sb-117
Sb-122
Sb-124
Sb-125
Sb-126
Sb-126m
Sb-127
Sb-129
Sc-44
SC-46
Sc-47
Sc-48
Sc-49
Se-73
Se-75
Se-79
Si-31
Si-32
Sm-147
Sm-151
Sm-153
Sn-113
Sn-117m
Sn-119m
3.6E-04
1.9E-01
9.3E+00
3.7E-01
1.7E+02
3.4E-01
8.3E-02
3.1E-03
2.9E-01
5.9E-04
7.5E-02
2.0E+00
3.9E-02
6.0E-04
1.4E-04
1.8E-03
7.6E-01
2.0E-02
1.8E-01
1.4E-01
4.0E-04
1.1E-01
1.1E-02
l.OE+01
1.6E-01
1.1E-03
6.9E-03
4.7E+00
7.2E-04
1.4E-05
3.5E-02
2.4E-01
1.9E-03
2.3E-02
2.8E-02
3.6E-01
1.9E+02
9.3E+03
3.7E+02
1.7E+05
3.4E+02
8.3E+01
3.1E+00
2.9E+02
5.9E-01
7.5E+01
2.0E+03
3.9E+01
6.0E-01
1.4E-01
1.8E+00
7.6E+02
2.0E+01
1.8E+02
1.4E+02
4.0E-01
1.1E+02
1.1E+01
l.OE+04
1.6E+02
1.1E+00
6.9E+00
4.7E+03
7.2E-01
1.4E-02
3.5E+01
2.4E+02
1.9E+00
2.3E+01
2.8E+01
3.6E+02
1.9E+05
9.3E+06
3.7E+05
1.7E+08
3.4E+05
8.3E+04
3.1E+03
2.9E+05
5.9E+02
7.5E+04
2.0E+06
3.9E+04
6.0E+02
1.4E+02
1.8E+03
7.6E+05
2.0E+04
1.8E+05
1.4E+05
4.0E+02
1.1E+05
1.1E+04
l.OE+07
1.6E+05
1.1E+03
6.9E+03
4.7E+06
7.2E+02
1.4E+01
3 . 5E.+04
2.4E+05
1.9E+03
2.3E+04
2.8E+04
See footnotes at the end of the table.
3-17
-------
Table 3-1
Radionuclide
Annual Possession Quantities for Environmental
Compliance (continued)
Annual Possession Quantities (Ci/yr)
Liquid/
Gaseous Powder Solid
Form* Forms Form*
Sn-123
Sn-125
Sn-126
Sr-82
Sr-85
Sr-85m
Sr-87m
Sr-89
Sr-90
Sr-91
Sr-92
Ta-182
Tb-157
Tb-160
Tc-95
Tc-95m
Tc-96
Tc-96m
Tc-97
Tc-97m
Tc-98
Tc-99
Tc-99m
Tc-101
Te-121
Te-121m
Te-123
Te-123m
Te-125m
Te-127
Te-127m
Te-129
Te-129m
Te-131
Te-131m
1.8E-02
7.2E-03
4.7E-06
1.9E-03
1.9E-03
1.5E+00
1.2E+00
2.1E-02
5.2E-04
1.2E-01
2.5E-01
4.4E-04
2.2E-03
8.4E-04
9.0E-02
1.4E-03
5.6E-03
7.0E-01
1.5E-03
7.2E-02
6.4E-06
9.0E-03
1.4E+00
3.8E+00
6.0E-03
5.3E-04
1.2E-03
2.7E-03
1.5E-02
2.9E+00
7.3E-03
6.5E+00
6.1E-03
9.4E-01
1.8E-02
1.8E+01
7.2E+00
4.7E-03
1.9E+00
1.9E+00
1.5E+03
1.2E+03
2.1E+01
5.2E-01
1.2E+02
2.5E+02
4.4E-01
2.2E+00
8.4E-01
9.0E+01
1.4E+00
5.6E+00
7.0E+02
1.5E+00
7.2E+01
6.4E-03
9.0E+00
1.4E+03
3.8E+03
6.0E+00
5.3E-01
1.2E+00
2.7E+00
1.5E+01
2.9E+03
7.3E+00
6.5E+03
6.1E+00
9.4E+02
1.8E+01
1.8E+04
7.2E+03
4.7E+00
1.9E+03
1.9E+03
1.5E+06
1.2E+06
2.1E+04
5.2E+02
1.2E+05
2.5E+05
4.4E+02
2.2E+03
8.4E+02
9.0E+04
1.4E+03
5.6E+03
7.0E+05
1.5E+03
7.2E+04
6.4E+00
9.0E+03
1.4E+06
3.8E+06
6.0E+03
5.3E+02
1.2E+03
2.7E+03
1.5E+04
2.9E+06
7.3E+03
6.5E+06
6.1E+03
9.4E+05
1.8E+04
See footnotes at the end of the table.
3-18
-------
Table 3-1
Annual Possession Quantities for Environmental
Compliance (continued)
Radionuclide
Annual Possession Quantities (Ci/yr)
Liquid/
Gaseous Powder Solid
Form* Forms Form"
Te-132
Te-133
Te-133m
Te-134
Th-226
Th-227
Th-228
Th-229
Th-230
Th-231
Th-232
Th-234
Ti-44
Ti-45
Tl-200
Tl-201
Tl-202
Tl-204
Tm-170
Tm-171
U-230
U-231
U-232
U-233
U-234
U-235
U-236
U-237
U-238
U-239
U-240
V-48
V-49
W-181
W-185
6.2E-03
1.2E+00
2.9E-01
4.4E-01
3.0E-02
6.4E-05
2.9E-06
4.9E-07
3.2E-06
8.4E-01
6.0E-07
2.0E-02
5.2E-06
4.0E-01
4.4E-02
1.8E-01
l.OE-02
2.5E-02
2.4E-02
5.9E-02
5.0E-05
1.4E-01
1.3E-06
7.6E-06
7.6E-06
7.0E-06
8.4E-06
4.7E-02
8.6E-06
8.3E+00
1.8E-01
1.4E-03
1.3E+00
1.1E-02
1.6E-01
6.2E+00
1.2E+03
2.9E+02
4.4E+02
3.0E+01
6.4E-02
2.9E-03
4.9E-04
3.2E-03
8.4E+02
6.0E-04
2.0E+01
5.2E-03
4.0E+02
4.4E+01
1.8E+02
l.OE+01
2.5E+01
2.4E+01
5.9E+01
5.0E-02
1.4E+02
1.3E-03
7.6E-03
7.6E-03
7.0E-03
8.4E-03
4.7E+01
8.6E-03
8.3E+03
1.8E+02
1.4E+00
1.3E+03
1.1E+01
1.6E+02
6.2E+03
1,2E+06
2.9E+05
4.4E+05
3.0E+04
6.4E+01
2.9E+00
4.9E-01
3.2E+00
8.4E+05
6.0E-01
2.0E+04
5.2E+00
4.0E+05
4.4E+04
1.8E+05
l.OE+04
2.5E+04
2.4E+04
5.9E+04
5.0E+01
1.4E+05
1.3E+00
7.6E+00
7.6E+00
7.0E+00
8.4E+00
4.7E+04
8.6E+00
8.3E+06
1.8E+05
1.4E+03
1.3E+06
1.1E+04
1.6E+05
See footnotes at the end of the table.
3-19
-------
Table 3-1
Radionuclide
Annual Possession Quantities for Environmental
Compliance (continued)
Annual Possession Quantities (Ci/yr)
Liquid/
Gaseous Powder Solid
Form* Forms Form*
W-187
W-188
Xe-122
Xe-123
Xe-125
Xe-127
Xe-129m
Xe-l31m
Xe-133
Xe-133m
Xe-135
Xe-135m
Xe-138
Y-86
Y-87
Y-88
Y-90
Y-90m
Y-91
Y-91m
Y-92
Y-93
Yb-169
Yb-175
Zn-62
Zn-65
Zn-69
Zn-69m
Zr-86
Zr-88
Zr-89
Zr-93
Zr-95
Zr-97
1.1E-01
l.OE-02
7.6E-02
1.6E+00
6.0E-01
7.0E+00
7.6E+01
2.2E+02
5.2E+01
6.0E+01
7.6E+00
4.2E+00
9.9E-01
2.8E-02
2.3E-02
2.5E-04
1.1E-01
4.3E-01
1.8E-02
1.6E+00
7.0E-01
3.8E-01
5.5E-03
2.1E-01
8.6E-02
4.4E-04
2.7E+01
2.0E-01
2.4E-02
2.7E-04
1.6E-02
2.8E-03
6.4E-04
4.6E-02
1.1E+02
l.OE+01
7.6E+01
1.6E+03
—
—
-
-
-
—
—
-
-
2.8E+01
2.3E+01
2.5E-01
1.1E+02
4.3E+02
1.8E+01
1.6E+03
7.0E+02
3.8E+02
5.5E+00
2.1E+02
8.6E+01
4.4E-01
2.7E+04
2.0E+02
2.4E+01
2.7E-01
1.6E+01
2.8E+00
6.4E-01
4.6E+01
1.1E+05
1 . OE+04
7.6E+04
1.6E+06
—
—
-
-
-
—
_
—
-
2.8E+04
2.3E+04
2.5E+02
1.1E+05
4.3E+05
1.8E+04
1.6E+06
7.0E+05
3.8E+05
5.5E+03
2.1E+05
8.6E+04
4.4E+02
2.7E+07
2.0E+05
2.4E+04
2.7E+02
1.6E+04
2.8E+03
6.4E+02
4.6E+04
* Radionuclides boiling at 100 °C or less, or exposed to a temperature of
100 °C or more, must be considered to be a gas.
"" Mo-99 contained in a generator to produce technetium-99 can be assumed
to be a solid.
3-20
-------
WORKSHEET C - CONCENTRATION TABLE
INTRODUCTION
The Concentration Table provides another simple method for determining
compliance and exemption from reporting by using measured concentrations
of each nuclide in each stack or vent. You may use this worksheet only
if both of the following conditions are satisfied:
1. All of your releases are from stacks or vents and you have measured
values of the concentrations. The measurements must have been made
using EPA-approved methods (EPA89b).
2. The distance between each stack or vent and the nearest receptor
must be greater than 3 times the diameter of the stack or vent.
See Figure 3-1 for the definition of this distance. If the stack
or vent is not circular, you can determine its diameter from D =
(1.3A)"2, where A is the area of the stack or vent.
EXPLANATION OF WORKSHEET C ITEMS
1. Enter the name of each nuclide being released. If the same nuclide
is released from more than one stack or vent, enter its name only
once.
2. Enter the average annual concentration of each nuclide listed in
step 1. If the same nuclide is released from more than one stack
or vent, enter the highest concentration of that nuclide in any
stack or vent. Concentration measurements must be based on
EPA-approved measurement techniques (EPA89b). Use of alternative
techniques must have prior approval of the EPA.
3-21
-------
In some cases, concentrations are measured in terms of gross alpha
or gross beta activity. These measurements may be used to
determine the concentrations of the individual radionuclides that
produce the gross activity measurement. However, you must justify
the method you use to do this, and it is allowed only when the
effluent is known to contain only a single nuclide, or the identity
and isotopic ratio of a mixture of nuclides are well known.
If you cannot determine the individual concentrations of the gross
activity measurements, you must assume that all the activity is
that of the most hazardous nuclide that could be present. To
determine which nuclide is the most hazardous, find the nuclide
among your releases that has the smallest concentration in Table
3-2. The concentration of gross activity in the stack is then
taken to be that nuclide's.
3. If you use radionuclides that are not listed in Table 3-2, contact
the EPA.
4. Self-explanatory.
5. Self-explanatory.
6. The division by 4 accounts for the frequency with which the wind
blows in any given direction.
7. SeIf-explanatory-
8. See explanation to 6 above.
3-22
-------
WORKSHEET C - CONCENTRATION TABLE
Facility Name:
Assessment Period (dates):
1. Enter the name of
each nuclide; i.e.,
1-131, Co-60, etc.
2. Enter the maximum
concentration of each
nuclide (Ci/m3) .
3. Enter the concen-
tration of each nu-
clide from Table 3-2.
4. Divide line 2 by
line 3.
5. Sum the fractions
on line 4.
6. Divide line 5 by 4.0.
7. Sum the fractions
on line 4 that are
due to radioiodines.
8. Divide line 7 by 4.0.
If the value on line 6 is less than 0.1 and the value on line 8 is less
than 0.03 and both represent the dose caused by the entire facility with
any new construction or modification, you are exempt from reporting or
submitting an application to construct or modify. If the value on line
6 is less than 0.01 and the value on line 8 is less than 0.003 and both
represent the dose caused only by any new construction or modification,
you are exempt from applying for an application to construct or modify
that would otherwise be required under 40 CFR 61, Subpart I. Retain
this worksheet for possible review by the EPA.
If the value on line 6 is equal to or greater than 0.1 but less than or
equal to 1.0, and the value on line 8 is equal to or greater than 0.03
but less than or equal to 0.3, you are in compliance but are not exempt
from reporting to the EPA. If the value on line 6 is equal to or
greater than 0.01, or the
3-23
-------
value on line 8 is equal to or greater than 0.003, and both represent
the dose caused only by any new construction or modification, you are
not exempt from reporting to the EPA. You may, if you like, use a
different method to determine if you are exempt. Retain this worksheet
for possible use later.
If the value on line 6 is greater than 1.0 or the value on line 8 is
greater than 0.3, you have not demonstrated compliance. You should use
another method to determine if you can meet the standard.
3-24
-------
Table 3-2. Concentration Levels for Environmental Compliance
Radionuclide
Concentration
(Ci/m3) Radionuclide
Concentration
(Ci/m3)
Ac-225
Ac-227
Ac-228
Ag-106
Ag-106m
Ag-108m
Ag-llOm
Ag-111
Al-26
Am-241
Am-242
Am-242m
Am-243
Am-244
Alll-245
Am-246
Ar-37
Ar-41
As-72
As-73
As-74
As-76
As-77
At-211
Au-193
Au-194
Au-195
AU-198
Au-199
Ba-131
Ba-133
Ba-133m
Ba-135m
Ba-139
Ba-140
Ba-141
Ba-142
Be-7
Be-10
Bi-206
9.1E-14
1.6E-16
3.7E-12
1.9E-09
1.2E-12
7.1E-15
9.1E-14
2.5E-12
4.8E-15
1.9E-15
1.5E-11
2.0E-15
1.8E-15
4.0E-11
8.3E-09
1.2E-09
1.6E-03
1.7E-09
2.4E-11
1.1E-11
2.2E-12
5.0E-11
1.6E-10
1.1E-11
3.8E-10
3.2E-11
3.1E-12
2.1E-11
4.8E-11
7.1E-12
5.9E-14
5.9E-11
1.8E-10
5.6E-09
1.3E-12
1.4E-09
1.3E-09
2.3E-11
1.6E-12
2.3E-12
Bi-207
Bi-210
Bi-212
Bi-213
Bi-214
Bk-249
Bk-250
Br-77
Br-80
Br-80m
Br-82
Br-83
Br-84
C-ll
C-14
Ca-41
Ca-45
Ca-47
Cd-109
Cd-113
Cd-113m
Cd-115
Cd-115m
Cd-117
Cd-117m
Ce-139
Ce-141
Ce-143
Ce-144
Cf-248
Cf-249
Cf-250
Cf-251
Cf-252
Cf-253
Cf-254
Cl-36
Cl-38
Cm-242
Cm-243
l.OE-14
2.9E-13
5.6E-11
7.1E-11
1.4E-10
5.6E-13
9.1E-11
4.2E-11
1.4E-08
1.8E-09
1.2E-11
1.2E-08
6.7E-10
1.5E-09
l.OE-11
4.2E-13
1.3E-12
2.4E-12
5.9E-13
9.1E-15
1.7E-14
1.6E-11
8.3E-13
6.7E-11
1.6E-10
2.6E-12
6.3E-12
3.0E-11
6.2E-13
1.8E-14
1.4E-15
3.2E-15
1.4E-15
5.6E-15
3.1E-13
3.0E-15
2.7E-15
7.7E-10
5.3E-14
2.6E-15
3-25
-------
Table 3-2. Concentration Levels for Environmental Compliance (cont.)
Radionuclide
Concentrat ion
(Ci/m3) Radionuclide
Concentration
(Ci/m3)
Cm-244
Cm-245
Cm-246
Cm-247
Cm-248
Cm-249
Cm-250
Co-56
Co-57
Co-58
Co-58m
Co-60
Co- 6 Om
CO-61
Cr-49
cr-51
Cs-129
Cs-131
Cs-132
CS-134
Cs-134m
Cs-135
Cs-136
Cs-137
Cs-138
Cu-61
Cu-64
Cu-67
Dy-157
Dy-165
Dy-166
Er-169
Er-171
Es-253
Es-254
ES-254TO
Eu-152
Eu-152m
Eu-154
Eu-155
3.3E-15
1.8E-15
1.9E-15
1.9E-15
5.0E-16
3.7E-09
9.1E-17
1.8E-13
1.3E-12
6.7E-13
1.2E-10
1.7E-14
4.3E-09
4.5E-09
1.1E-09
3.1E-11
1.4E-10
3.3E-11
4.8E-12
2.7E-14
1.7E-10
4.0E-13
5.3E-13
1.9E-14
5.3E-10
4.8E-10
5.3E-10
5.0E-11
5.0E-10
6.7E-09
1.1E-11
2.9E-11
4.0E-10
2.4E-13
2.0E-14
1.8E-12
2.0E-14
3.6E-10
2.3E-14
5.9E-13
Eu-156
F-18
Fe-52
Fe-55
Fe-59
Fm-254
Fm-255
Fr-223
Ga-66
Ga-67
Ga-68
Ga-72
Gd-152
Gd-153
Gd-159
Ge-68
Ge-71
Ge-77
H-3
Hf-181
Hg-193m
Hg-197
Hg-197m
Hg-203
Ho-166
Ho- 16 6m
1-123
1-124
1-125
1-126
1-128
1-129
1-130
1-131
1-132
1-133
1-134
1-135
In-Ill
In-113m
1.9E-12
6.7E-10
5.6E-11
9.1E-12
6.7E-13
2.0E-11
4.3E-12
3.3E-11
6.2E-11
7.1E-11
9.1E-10
3.8E-11
5.0E-15
2.1E-12
2.9E-10
2.0E-13
2.4E-10
l.OE-10
1.5E-09
1.9E-12
l.OE-10
8.3E-11
1.1E-10
l.OE-12
7.1E-11
7.1E-15
4.3E-10
6.2E-13
1.2E-13
1.1E-13
1.1E-08
9.1E-15
4.5E-11
2.1E-13
2.3E-10
2.0E-11
3.8E-10
1.2E-10
3.6E-11
2-. 5E-09
3-26
-------
Table 3-2. Concentration Levels for Environmental Compliance Xcont.)
Radionuclide
Concentration
(Ci/m3)
Radionuclide
Concentration
(Ci/m3)
In-114m
In-115
In-115m
In-116m
In-117
In-117m
Ir-190
Ir-192
Ir-194
Ir-194m
K-40
K-42
K-43
K-44
Kr-79
Kr-81
Kr-83m
Kr-85
Kr-85m
Kr-87
Kr-88
La-140
La-141
La-142
Lu-177
Lu-177m
Mg-28
Mn-52
Mn-52m
Mn-53
Mn-54
Mn-56
Mo-93
Mo- 9 9
Mo-101
Na-22
Na-24
Nb-90
Nb-93m
Nb-94
9.1E-13
7.1E-14
1.6E-09
4.2E-10
1.6E-09
9.1E-11
2.6E-12
9.1E-13
1.1E-10
1.7E-13
2.7E-14
2.6E-10
6.2E-11
5.9E-10
8.3E-09
2.1E-07
2.3E-05
l.OE-06
1.3E-08
2.4E-09
5.0E-10
1.2E-11
7.7E-10
2.7E-10
2.4E-11
3.6E-13
1.5E-11
2.8E-12
6.2E-10
1.5E-11
2.8E-13
2.9E-10
1.1E-12
1.4E-11
l.OE-09
2.6E-14
2.6E-11
2.6E-11
l.OE-11
7.1E-15
Nb-95
Nb-95m
Nb-96
Nb-97
Nd-147
Nd-149
Ni-56
Ni-57
Ni-59
Ni-63
Ni-65
Np-235
Np-237
Np-238
Np-239
Np-240
Np-240m
Os-185
Os-191m
Os-191
Os-193
P-32
P-33
Pa-230
Pa-231
Pa-233
Pa-234
Pb-203
Pb-205
Pb-209
Pb-210
Pb-211
Pb-212
Pb-214
Pd-103
Pd-107
Pd-109
Pm-143
Pm-144
Pm-145
2.2E-12
1.4E-11
2.4E-11
1.2E-09
7.7E-12
7.1E-10
1.7E-12
1.8E-11
1.5E-11
1.4E-11
8.3E-10
2.5E-11
1.2E-15
1.4E-11
3.8E-11
7.7E-10
5.6E-09
l.OE-12
2.9E-10
1.1E-11
9.1E-11
3.3E-13
2.4E-12
3.2E-13
5.9E-16
4.8E-12
1.1E-10
6.2E-11
5.6E-12
1.3E-08
2.8E-15
1.4E-10
6.3E-12
1.2E-10
3.8E-11
3.1E-11
4.8E-10
9.1E-13
1.3E-13
6.2E-13
3-27
-------
Table 3-2. Concentration Levels for Environmental Compliance .(cont.)
Concentration
Radionuclide (Ci/m3) Radionuclide
Concentration
(Ci/m3)
Pm-146
Pm-147
Pm-148
Pm-148m
Pm-149
Pm-151
Po-210
Pr-142
Pr-143
Pr-144
Pt-191
Pt-193
Pt-193m
Pt-195m
Pt-197
Pt-197m
Pu-236
Pu-237
Pu-238
Pu-239
Pu-240
Pu-241
Pu-242
PU-243
Pu-244
Pu-245
Pu-246
Ra-223
Ra-224
Ra-225
Ra-226
Ra-228
Rb-81
Rb-83
Rb-84
Rb-86
Rb-87
Rb-88
Rb-89
Re-184
5.3E-14
1.1E-11
5.0E-12
6.7E-13
4.2E-11
7.1E-11
7.1E-15
1.1E-10
7.1E-12
1.8E-08
4.3E-11
1.8E-11
4.8E-11
3.2E-11
4.0E-10
2.6E-09
5.9E-15
1.9E-11
2.1E-15
2.0E-15
2.0E-15
l.OE-13
2.0E-15
4.2E-09
2.0E-15
2.1E-10
2.2E-12
4.2E-14
1.5E-13
5.0E-14
3.3E-15
5.9E-15
5.0E-10
3.4E-13
3.6E-13
5.6E-13
1.6E-13
2.1E-09
7.1E-10
1.5E-12
Re-184m
Re-186
Re-187
Re-188
Rh-103m
Rh-105
Ru-97
Ru-103
Ru-105
Ru-106
S-35
Sb-117
Sb-122
Sb-124
Sb-125
Sb-126
Sb-126m
Sb-127
Sb-129
Sc-44
Sc-46
Sc-47
Sc-48
Sc-49
Se-73
Se-75
Se-79
Si-31
Si-32
Sm-147
Sm-151
Sm-153
Sn-113
Sn-117m
Sn-119m
Sn-123
Sn-125
Sn-126
Sr-82
Sr-85
3.7E-13
1.8E-11
2.6E-10
1.7E-10
2.1E-07
1.3E-10
6.7E-11
2.6E-12
2.8E-10
3.4E-13
1.3E-12
2.4E-09
1.4E-11
5.3E-13
1.6E-13
1.4E-12
9.1E-10
7.1E-12
7.7E-11
1.7E-10
4.2E-13
3.8E-11
9.1E-12
1.2E-08
1.7E-10
1.7E-13
1.1E-13
5.6E-09
3.4E-14
1.4E-14
2.1E-11
5.9E-11
1.4E-12
5.6E-12
5.3E-12
1.1E-12
1.7E-12
5.3E-15
6.2E-13
1.8E-12
3-28
-------
Table 3-2. Concentration Levels for Environmental Compliance (cont.)
Concentration Concentration
Radionuclide (Ci/m3) Radionuclide (Ci/m3)
Sr-85m
Sr-87m
Sr-89
Sr-90
Sr-91
Sr-92
Ta-182
Tb-157
Tb-160
Tc-95
Tc-95m
Tc-96
Tc-96m
Tc-97
Tc-97m
Tc-98
Tc-99
Tc-99m
Tc-101
Te-121
Te-121m
Te-123
Te-123m
Te-125m
Te-127
Te-127m
Te-129
Te-129m
Te-131
Te-131m
Te-132
Te-133
Te-133m
Te-134
Th-226
Th-227
Th-228
Th-229
Th-230
Th-231
1.6E-09
1.4E-09
1.8E-12
1.9E-14
9.1E-11
2.9E-10
4.5E-13
2.5E-12
7.7E-13
l.OE-10
1.4E-12
5.6E-12
6.7E-10
7.1E-13
7.1E-12
6.7E-15
1.4E-13
1.7E-09
4.5E-09
l.OE-12
1.2E-13
1.4E-13
2.0E-13
3.6E-13
l.OE-09
1.5E-13
7.7E-09
1.4E-13
9.1E-11
l.OE-12
7.1E-13
9.1E-10
2.2E-10
5.3E-10
3.4E-11
3.8E-14
3.1E-15
5.3E-16
3.4E-15
2.9E-10
Th-232
Th-234
Ti-44
Ti-45
Tl-200
Tl-201
Tl-202
Tl-204
Tm-170
Tm-171
U-230
U-231
U-232
U-233
U-234
U-235
U-236
U-237
U-238
U-239
U-240
V-48
V-49
W-181
W-185
W-187
W-188
Xe-122
Xe-123
Xe-125
Xe-127
Xe-129m
Xe-131m
Xe-133
Xe-133m
Xe-135
Xe-135m
Xe-138
Y-86
Y-87
6.2E-16
2.2E-12
6.2E-15
4.8E-10
4.5E-11
l.OE-10
5.0E-12
1.2E-12
3.3E-12
2.6E-11
1.5E-14
4.2E-11
1.3E-15
7.1E-15
7.7E-15
7.1E-15
7.7E-15
l.OE-11
8.3E-15
4.3E-09
1.3E-10
l.OE-12
1.6E-10
6.7E-12
2.6E-12
7.7E-11
5.3E-13
9.1E-11
1.6E-09
1.1E-11
8.3E-09
9.1E-08
2.6E-07
6.2E-08
7.1E-08
9.1E-09
5.0E-09
1.2E-09
3.0E-11
1.7E-11
3-29
-------
Table 3-2. Concentration Levela for Environmental Compliance {cont.)
Radionuclide
Concentration
(Ci/m3) Radionuclide
Concentration
(Ci/m3)
Y-88
Y-90
Y-90m
Y-91
Y-91m
Y-92
Y-93
Yb-169
Yb-175
Zn-62
2.7E-13
1.3E-11
1.9E-10
2.1E-12
1.3E-09
8.3E-10
2.9E-10
3.7E-12
4.3E-11
9.1E-11
Zn-65
Zn-69
Zn-69m
Zr-86
Zr-88
Zr-89
Zr-93
Zr-95
Zr-97
9.1E-14
3.2E-08
1.7E-10
2.4E-11
3.1E-13
1.3E-11
2.6E-12
6.7E-13
3.8E-11
3-30
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WORKSHEET D - STACK OR VENT CHARACTERISTICS
INTRODUCTION
Worksheet D is provided for use in keeping track of the various
release points. Even if your facility has no releases from stacks
or vents*, fill out this worksheet.
If you have many release points and would like to reduce book-
keeping requirements, you may assume that all the radionuclides
from your facility are released from the stack or vent having the
potential for causing the highest dose. Similarly, you may assume
that all the release points from a building can be replaced by a
single stack or vent having the potential for causing the highest
dose. In either case, the stack or vent having the potential for
causing the highest dose must be determined by running COMPLY with
a unit release of any one of your radionuclides from a selection of
stacks or vents. The selection should be based on factors such as
distance to the receptor, building configuration and meteorological
data if a wind rose is used. If you consolidate releases, you must
make the stack or vent height no greater than the building height.
Alternative procedures for consolidating releases may be used if
you have approval from the EPA.
If none of your releases are from stacks or vents, write in "no
stacks" on line 1. On line 2 put N/A. Enter 0.03 on line 3 and
0.1 on line 4. Enter a 1 on line 5.
* The calculations do not distinguish between a stack and
a vent. We include both terms for completeness.
3-31
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EXPLANATION OF WORKSHEET D ITEMS
1. Self-explanatory.
2 . This item is for your own use in identifying which release
point is which. For example, you might enter "Roof vent from
building X" here.
3. This is the volumetric flow rate out of the stack. If you do
not have measured flow rates, use the name plate rating of
the fan. If the temperature of the air flowing through the
stack or vent is significantly different from that of the air
flowing through the fan, the volumetric flow rate up the
stack will be different than that through the fan. With a
100-degree Fahrenheit temperature difference, the change in
flow could be on the order of 20 percent.
The correction for temperature is as follows:
where the Qs are the flow rates and the Ts are the absolute
temperatures (degrees C + 273 or degrees F + 460) .
4. This is the inside diameter at the point of release. If the
stack or vent is not circular, determine its equivalent
circular diameter from
D = (1.3A)1/2, where A is the stack flow area.
5. The stack height is the distance from the ground to the top
of the stack or the center of a vent from the side of a
building. See Figure 3-2 at the end of this section.
3-32
-------
6. See Figure 3-1.
7. This is needed only when you use level 4 of the COMPLY code.
It should be the annual average.
8. This is needed only when you use level 4 of the COMPLY code.
It should be the average temperature during the operation.
3-33
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WORKSHEET D - STACK OR VENT CHARACTERISTICS
Facility Name:
Assessment Period (dates):
1. Stack number (to
keep track of
each stack as
you proceed)
2. Stack or v-nt
identity (lor
your infor-
mation only)
3. Stack flow
rate, m3/s(A)
4. Stack inside
diameter, m
5. Stack height, m
6. Distance to
closest resi-
dent, m®
7. Ambient air
temp. ,°F(Q
8. Stack gas
temp.,°F(C)
(A) To obtain m3/sec from cfm, multiply cfm by 4.72x10"*.
(B) Not needed if wind rose used (level 4 of COMPLY code)
(C) Needed only for level 4 of COMPLY code.
3-34
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WORKSHEET E - RELEASE RATES
INTRODUCTION
Release rates are needed if you either calculate dose by hand or
use the computer code to determine whether you are in compliance
with the standard. Release rates from tailing piles should be
calculated using procedures described in NRC87. Otherwise, use
this to calculate release rates.
You will need the information in 1, 2, or 3 below.
1. The average annual release rate for each nuclide in each
stack or vent (curies/year).
or
2(a). The average annual concentration of each nuclide measured in
each stack or vent (curies/m3) , and
2(b). The stack flow rate (in cubic meters/second).
or
3 (a). The annual possession quantities from line 4 of Worksheet B,
and
3 (b) . The physical form of each radionuclide from line 5 of
Worksheet B.
You will need either NCRP Commentary No. 3 or the User's Guide for
the COMPLY Code. See Section 5.2, Sources, for information on how
obtain these documents and the COMPLY code.
3-35
-------
EXPLANATION OF WORKSHEET E ITEMS
1. You will need to complete one of these worksheets for each
stack or vent. If you have more than one stack or vent,
complete Worksheet D.
2. If you intend to use the measured stack concentrations or the
measured release rates, enter the name of each nuclide being
released. If you intend to use the annual posses-
sion amounts to compute the release rates (steps 7-12) and a
nuclide is in more than one physical form (gas, liquid or
powder, or solid) , enter its name once for each physical
form. See the explanation for line 5 of Worksheet B for
restrictions on these physical forms.
3. Release rate measurements must be based on EPA-approved
measurement techniques (EPA89b). Use of alternative
techniques must have prior approval from the EPA.
In some cases, concentration measurements are made in terms
of gross alpha or gross beta activity. These may be used to
determine the concentrations of the individual radionuclides
that produce the gross activity measure-
ment. However, you must justify the method you use to do
this, and it is allowed only when the effluent is known to
contain only a single nuclide, or the identity and isotopic
ratio of a mixture of nuclides are well known.
If you cannot determine the individual concentrations from
the gross activity measurements, you must assume that all the
activity is that of the most hazardous nuclide that could be
present. To determine which nuclide is the most
3-36
-------
hazardous, find t^e nuclide among your releases that has the
smallest concentration in Table 3-2. The concen-
tration of gross activity in the stack is then taken to be
that nuclide's.
4. Concentration measurements must be based on EPA-approved
measurement techniques (EPA89b) . If your measurements are in
terms of gross alpha or gross beta activity, see item 3
above.
5. This is the volumetric flow rate up the stack or vent in
cubic meters/year. If your flow rate is in terms of m3/s,
multiply by 3.2xl07 to get m3/yr. If your flow is in terms of
ft3/min, multiply by 1.5xl04 to get m3/yr.
6. Self-explanatory.
7. If you have neither measured release rates nor measured
concentrations, you may use the annual possession quantities
to estimate the release rates. Fill out lines 1-4 of
Worksheet B (if you have not already done so) and enter the
values from line 4 of Worksheet B here. You can link a
particular quantity to a particular stack or vent only if you
can justify it. For example, if a specific area is vented
only through a given stack, and you know the amounts on hand
and the amounts received for that area, then you may
calculate the concentration for that stack from that
possession quantity. Otherwise, you must assume that all the
nuclides escape through the stack nearest to the closest
receptor.
8. This must be a gas, a liquid or powder, or a solid.
3-37
-------
If any nuclide is exposed to a temperature of 100 degrees
Celsius or more, or boils at temperatures of 100 degrees
Celsius or less, it must be considered a gas.
9. Self-explanatory.
10. Enter the appropriate values from Table 3-3. If there are no
control devices, enter 1.0.
11. Self-explanatory.
12. Sum the release rates for nuclides having the same name. For
example, if on line 2, 1-131 was listed twice because you
have it in both the liquid and solid form, add the two 1-131
release rates together.
13. There should be a worksheet for each stack or vent.
3-38
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WORKSHEET E - RELEASE RATES
Facility Name:
Assessment Period (dates):
1. Stack No. of
2. Enter the name of
each nuclide (i.e.,
1-131, Co-60, etc.).
3. If you have measured
release rates (Ci/yr)
using EPA-approved
techniques, enter
them and go to line
12. Otherwise go to
line 4.
4. If you have measured
concentrations (Ci/m3)
by EPA-approved
methods, enter
them. Otherwise
go to line 7.
5. Enter the stack
flow rate, m3/yr.
If you do not know
the flow rate, go
to line 7.
6. Multiply the values
on line 4 by the
flow rate on line 5.
These are the re-
lease rates (Ci/yr).
Go to line 12.
7. If you do not have
measured concen-
trations or release
rates, enter the
annual possession
amounts (Ci) from
line 4 of Worksheet B.
If you have not filled
out lines 1-4 of
Worksheet B, do so now.
3-39
-------
Worksheet E (page 2 of 2)
Facility Name:
Assessment Period (dates):
Stack No. of
8. Enter the physical
form of each nuclide
from line 5 of Work-
sheet B.
9. For each nuclide,
enter 1.0 if line 8
is a gas, 0.001 if
line 8 is a liquid
or powder, or 10"6
if line 8 is a
solid.
10. Enter the appro-
priate values from
Table 3-3. Enter
1.0 if there are
no controls.
11. Multiply line 7 by
lines 9 and 10.
These are the re-
lease rates in
Ci/year.
12. Sum the release
rates for nuclides
having the same name.
13. Repeat this worksheet for each stack or vent if you
have more than one.
Use the release rates on line 11 or 12 as input for either the hand
calculations described in NCRP Commentary No. 3, or the COMPLY
computer code.
3-40
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Table 3-3. Adjustments to emission factors for effluent controls
Control
Types of
Radionuclides
Controlled
Adjustment
Factor to
Emissions
Comments
and
Conditions
HEPA Filters
Particulates
0.01
Not applicable
to gaseous
radionuclides;
periodic testing
is prudent to
ensure high
removal efficiency
Fabric Filters
Particulates
0.1
Sintered Metal Filters
Activated Carbon
Filters
Particulates
Iodine Gas
0.1
Monitoring
would be
prudent to
guard against
tears in filter
Insufficient
data to make
recommendation
Efficiency is
time dependent;
monitoring
is necessary
to ensure
effectiveness
Douglas Bags:
Held one week or Xenon
longer for decay
Released within Xenon
one week
0.5/wk Based on xenon
half-life
of 5.3 days;
1 Provides no
reduction of
exposure
to general
public
3-41
-------
Table 3-3. Adjustments to emission factors for effluent controls
Control
Types of
Airborne
Radionuclides
Controlled
Adjustment
Factor to
Emissions
Comments
and
Conditions
Venturi Scrubbers
Particulates
Gases
0.05
Packed Bed Scrubbers
Electrostatic
Precipitators
Xenon Traps
Gases
Particulates
Xenon
0.1
0.05
0.1
Fume Hoods
All
Vent Stacks
All
Although
Venturis may
remove gases,
variability
in gaseous
removal
efficiency
dictates
adjustment
factor for
particulates
only
Not applicable
to particulates
Not applicable
for gaseous
radionuclides
Efficiency is
time dependent;
monitoring is
necessary to
ensure
effectiveness
Provides no
reduction
to general
public
exposures
Generally
provides no
reduction of
exposure to
general public
3-42
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WORKSHEET F - COMPLY Code and NCRP COMMENTARY NO. 3
Facility Name:
Assessment Period (dates):
This worksheet describes how to interpret both the output of
the COMPLY computer code, and the results from the calculations of
NCRP Commentary No. 3. Note that certain steps of NCRP Commentary
No. 3 are not needed for this application. Follow the instructions
in NCRP Commentary No. 3 except as noted below.
Basis for Compliance
The basis for determining whether you are exempt from
reporting, in compliance, or not in compliance is as follows: If
the effective-dose equivalent from all radionuclides is equal to or
less than 10 mrem/yr, and the effective-dose equivalent from
radioiodine is equal to or less than 3 mrem/yr, you are in
compliance. If the effective-dose equivalent from all
radionuclides is less than 1 mrem/yr, and the effective-dose
equivalent from all radioiodines is less than 0.3 mrem/yr, and both
represent the dose caused by the entire facility including any new
construction or modification, you are exempt from reporting or
submitting an application to construct or modify to the EPA. If
the effective-dose equivalent from all radionuclides is less than
0.1 mrem/yr, and the effective-dose equivalent from all
radioiodines is less than 0.03 mrem/yr, and both represent the dose
caused by any new construction or modification only, you are exempt
from submitting an application to construct or modify.
NCRP Screening Level I
Enter the effective-dose equivalent for all radionuclides
here: mrem/yr and for all radioiodines here: mrem/yr.
See the Basis for Compliance given above to determine whether you
are in compliance or exempt from the reporting requirements.
If you are not in compliance, proceed to Screening Level II
of NCRP Commentary No. 3 or use COMPLY. If you are in compliance
but are not exempt from reporting, you may wish to proceed to NCRP
Screening Level II or use COMPLY to determine if you may be exempt.
COMPLY Level 1 (Possession and Concentration Tables)
Enter the possession or emission fraction for all
3-43
-------
radionuclides from COMPLY here and for radioiodines
here . Follow the instructions given after step 9 of
worksheet B. If the fraction is greater than 1.0 for all
radionuclides or 0.3 for radioiodines, you have not demonstrated
compliance. You should go to Levels 2 - 4 of COMPLY to determine
if you can meet the standard.
COMPLY Level 2 or NCRP Screening Level II
If you are using Level 2 of COMPLY or NCRP Commentary
No. 3, enter the effective dose equivalent from all radionuclides
here: mrem/yr and from radioiodines here: mrem/yr.
See the Basis for Compliance given above to determine whether
you are in compliance or exempt from the reporting requirements.
If you are in compliance, but are not exempt from reporting, you
may wish to proceed to either Level 3 of COMPLY or to NCRP
Screening Level III to determine if you may be exempt.
COMPLY Level 3 or NCRP Screening Level III
If you are using Level 3 of COMPLY or NCRP Commentary
No. 3, enter the effective-dose equivalent from all radionuclides
here: mrem/yr and from radioiodines here: mrem/yr.
See the Basis for Compliance given above to determine whether
you are in compliance or exempt from the reporting requirements.
If you are in compliance, but are not exempt from reporting, you
may wish to proceed to Level 4 of COMPLY to determine if you may be
exempt.
COMPLY Level 4
If you are using Level 4 of COMPLY, enter the effective-dose
equivalent from all radionuclides here: mrem/yr and from
radioiodines here: mrem/yr.
See the Basis for Compliance given above to determine whether
you are in compliance or exempt from the reporting requirements.
If you are not in compliance, you should contact your EPA radiation
representative. See Section 5.
3-44
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RELEASE POINT
RECEPTOR
(NEAREST RESIDENT
OR FARM)
d - DISTANCE TO NEAREST RECEPTOR OR FARM
Figure 3-2
Distance between source and
nearest receptor
3-45
-------
GROUND LEVEL v
o
H
T
H
hB - BUILDING HEIGHT
H -STACKHEIGHT
Figure 3-1. Stack and building heights
3-46
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4. REPORTING AND RECORDKEEPING REQUIREMENTS
4.1 REPORTING REQUIREMENTS
The owner or operator of an existing facility that is not exempt
from the reporting requirements must submit an annual report to the
EPA. The owner or operator of a new facility or one that is being
modified must file an application with the EPA unless his facility
is exempt. This report or application must provide the following
information:
GENERAL INFORMATION
1. The name of the facility.
2. The name of the person responsible for the operation of the
facility and the name of the person preparing the report (if
different).
3. The location of the facility, including suite and/or building
number, street, city, county, state, and zip code.
4. The mailing address of the facility, if different from item 3
DESCRIPTION OF THE FACILITY AND NEARBY ENVIRONMENT
5. A list of the radioactive materials used at the facility.
6. A description of the handling and processing that the
radioactive materials undergo at the facility.
7. A list of the stacks or vents or other points where
radioactive materials are released to the atmosphere.
4-1
-------
8. A description of the effluent controls that are used on each
stack, vent, or other release point and an estimate of the
efficiency of each device.
9. A plan view of the facility identifying:
a. the points where radioactive materials are released to
the air;
b. the location of the nearest receptor; and
c. the location of the nearest farm(s) where milk, meat, or
vegetables are grown. If the farms are difficult to
locate, you may estimate the distance. However, you must
be prepared to justify your selection.
10. The effective dose equivalent calculated using the compliance
procedures in 61.103.
11. All information required in an application to construct or
modify a facility under section 61 subpart A, for all
construction and modifications which were completed in the
relevant calendar year but for which the requirement to apply
for approval to construct or modify was waived under section
61.
PARAMETERS USED IN DOSE CALCULATIONS
Note: You should supply copies of all the Section 3 worksheets
used in making your dose estimates.
If you use the COMPLY computer code to make your dose esti-
mates, most of the information listed below will be printed as a
part of the output. You may submit a copy of this output as
4-2
-------
a part of your report and do not have to submit this information
separately. Your report, however, must include sufficient
information for the EPA to judge the validity of the input.
If you use NCRP Commentary No. 3 to make your dose estimates, you
may submit a copy of the NCRP Commentary No. 3 worksheets as part
of your report. You do not have to submit the information on the
worksheets separately. Again, your report must include enough
information for the EPA to judge the validity of the input used in
the calculations.
Not all the parameters listed below are needed for any given
facility. You do not have to report any that you do not use.
12. The physical form and quantity of each radionuclide emitted
from each stack, vent, or other release point and the
method(s) by which these quantities were determined.
13. The volumetric flow, diameter, effluent temperature, and
release height for each stack, vent, or other release point
where radioactive materials are emitted and the method(s) by
which these were determined.
14. The height, length, and width of each building from which
radionuclides are emitted.
15. Distances and directions from the point of release to the
nearest receptor and the nearest farms producing vegetables,
mdlk, and meat.
16. The values used for all other user-supplied input parameters
(e.g., meteorological data) and the source of these data.
4-3
-------
If the facility is not in compliance, then the facility must report
to the Administrator on a monthly basis. These reports will be due
30 days following the end of each month. This increased level of
reporting will continue until the Administrator has determined that
the monthly reports are no longer necessary. In addition to all
the information required above, monthly reports shall include the
following information:
17. All controls or other changes in operation of the facility
that will be or are being installed to bring the facility into
compliance.
18. If the facility is under a judicial or administrative
enforcement decree, the report will describe the facility's
performance under the terms of the decree.
4.2 Recordkeeping Requirements
The owner or operator of any facility subject to the standard must
maintain records documenting the source of input parameters, the
calculations and/or analytical methods used to derive values for
input parameters, and the procedure used to determine compliance.
In all cases, the documentation should be sufficient to allow an
independent auditor to verify whether the facility complies with
the standard, and qualifies for exemption from reporting or filing,
if claimed. These records must be kept at the site of the facility
for at least five years and upon request be made available for
inspection by the Administrator, or his authorized representative.
4-4
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5. RESOLVING PROBLEMS AND CONTACTING THE EPA
5.1 EPA CONTACTS
If you do not understand any steps or have trouble with any of the
calculations described in this document, you should contact the
Program Manager at your regional EPA office. You should also
contact the Program Manager if you are unable to demonstrate
compliance after having tried all the methods discussed in this
report, including level 4 of the COMPLY code. EPA Regional Offices
are depicted in Figure 5-1. A list of the regional EPA Program
Managers and their telephone numbers is included as Table 5-1.
While most facilities will be able to demonstrate compliance by one
of the methods described in this report, if none of these methods
works for your facility, you should contact the EPA Program Manager
at your regional EPA office to determine the next step.
5.2 SOURCES
NCRP Commentary No. 3 may be obtained from the National Council on
Radiation Protection and Measurements, 7910 Woodmont Avenue,
Bethesda, Maryland 20814. The telephone number is 301-657-2652.
Additional copies of this document, or the User's Guide for the
COMPLY Code and 5 1/4-inch diskettes containing the code and all
the data files can be obtained from:
Program Management Office (6601J)
Office of Radiation and Indoor Air
Environmental Protection Agency
401 M St., SW
Washington, DC 20460.
5-1
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Figure 1-1 EPA Regional Offices
PUERTO MOO
Regions
4 - Alabama
10-Alaska
9 — Arizona
6 ~ Arkansas
9 - California
8 - Colorado
1 ~ Connecticut
3 - Delaware
3 - D.C.
4 - Florida
4 - Georgia
9 - Hawaii
10 - Idaho
5 - Illinois
7 ~ Iowa
7 — Kansas
4 - Kentucky
6 - Louisana
Regions
1 -- Maine
3 - Maryland
1 - Massachusetts
5 - Michigan
5 - Minnesota
4 - Mississippi
7 — Missouri
8 - Montana
7 — Nebraska
9 - Nevada
1 - New Hampshire
2 -- New Jersey
6 - New Mexico
2 - New York
4 - North Carolina
5 - Ohio
6 - Oklahoma
10 -- Oregon
Regions
3 -- Pennsylvania
1 - Rhode Island
4 - South Carolina
8 -- South Dakota
4 -- Tennessee
6 -- Texas
8 - Utah
1 - Vermont
3 - Virginia
10 - Washington
3 - West Virginia
5 - Wisconsin
8 — Wyoming
9 - American Samoa
9 -- Guam
2 - Virgin Islands
5-2
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Table 1-1. EPA Regional Program Managers
Telephone No.
Tom D'Avanzo
Radiation Program Manager, Region 1
Environmental Protection Agency
John F. Kennedy Federal Building / ATR
One Congress Street
Boston, MA 02203
(617) 565-4502
Paul A Giardina
Radiation Program Manager, Region 2
Environmental Protection Agency
Jacob K. Javits Federal Building / 1005A
26 Federal Plaza
New York, NY 10278
(212) 264-4110
Lewis Felleisen
Radiation Program Manager, Region 3
Special Program Section
Environmental Protection Agency
841 Chestnut Street / 3AT12
Philadelphia, PA 19107
(215) 597-8326
Chuck Wakamo
Radiation Program Manager, Region 4
Environmental Protection Agency
345 Courtland Street, N.E.
Atlanta, GA 30365
(404) 347-3907
Jack Barnett
Radiation Program Manager, Region 5
Environmental Protection Agency
77 West Jackson Blvd. / AT18J
Chicago, IL 60604-3507
(312) 886-6175
Donna Ascenzi
Radiation Program Manager, Region 6
Air Program Branch (6T-E)
Air, Pesticides and Toxics Division
Environmental Protection Agency
1445 Ross Avenue
Dallas, TX 75202-2733
(214) 655-7224
5-3
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Table 5-1. EPA Regional Program Managers (continued)
Telephone No»
Robert Dye
Radiation Program Manager, Region 7 (913) 551-7605
Environmental Protection Agency
726 Minnesota Avenue
Kansas City, KS 66101
Milton W. Lammering
Radiation Program Manager, Region 8 (303) 293-1440
Environmental Protection Agency
Suite 500
999 18th street
Denver, CO 80202-2405
Michael S. Bandrowski
Radiation Program Manager, Region 9 (415) 744-1048
Environmental Protection Agency
75 Hawthorne Street (A-l-1)
San Francisco, CA 94105
Jerry Leitch
Radiation Program Manager, Region 10 (206) 553-7660
Environmental Protection Agency
1200 Sixth Avenue, Mail Stop AT-082
Seattle, WA 98101
5-4
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REFERENCES
NCRP89, "Screening Techniques for Determining Compliance with
Environmental Standards," NCRP Commentary No. 3, National Council
on Radiation Protection and Measurements, Revision of January, 1989
with Addendum of October, 1989.
NRC87, "Methods for Estimating Radioactive and Toxic Airborne
Source Terms for Uranium Milling Operations," U.S. Nuclear
Regulatory Commission Regulatory Guide 3.59, March 1987.
EPA89a, "User's Guide for the Comply Code," EPA 520/1-89-003, U.S.
Environmental Protection Agency, Office of Radiation Programs,
October 1989.
EPA89b, "Methods for Measuring Radionuclide Emissions from
Stationary Sources" as given in 40 CFR Part 61, Appendix B.
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