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.
                                 3-6

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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

-------
     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

-------
           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

-------
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

-------
           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

-------
                   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

-------
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

-------
    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

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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

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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

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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

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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

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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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