&EPA
United States
Environmental Protection
Agency
Office of Air Quality EMB Report No. 88-EPP-02
Planning and Standards Volume I
Research Triangle Park, NC 2771 1 January 1989
Air
Elemental Phosphorus
Production -
Calciner Off-Gases
Emission Test Report
FMC
Pocatello, Idaho
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DCN 89-222-124-26-02
Radian No. 222-124-26
EMISSION TEST REPORT
FMC ELEMENTAL PHOSPHORUS PLANT
POCATELLO, IDAHO
VOLUME I
EPA Contract No. 68-02-4338
Work Assignment No. 20
Prepared for:
Robert T. Harrison, Task Manager
Emissions Measurement Branch
Technical Support Division
U. S. Environmental Protection Agency
Research Triangle Park, North Carolina 27711
Prepared by:
Radian Corporation
Post Office Box 13000
Research Triangle Park, North Carolina 27709
January 1989
JES/045
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TABLE OF CONTENTS
VOLUME I
Section Page
1.0 EXECUTIVE SUMMARY 1 1
1.1 Introduction/Background 1 1
1.1.1 Test Program Objectives 1 1
1.1.2 Overview of Testing Activities 1-2
1.2 Summary of Emission Results 1-7
1.2.1 PM and Radionucl ides (MM 111) 1-7
1.2.2 Particulate Size Distribution 1-9
1.3 Test Report Organization 1-21
2.0 DESCRIPTION OF PROCESS AND AIR POLLUTION CONTROL SYSTEMS.... 2-1
2.1 Process Description 2-1
2.2 Air Pollution Control Equipment (Calcining Operation) . 2-3
2.3 Process and Pollution Control Data 2-3
2.3.1 Process Rate 2-4
2.3.2 Burner Temperatures 2-4
2.3.3 Fan Amperage 2-4
2.3.4 Pressure Drop ( p) Across Each Venturi Scrubber. 2-11
2.3.5 Scrubber Liquid Flow Rate for Each Scrubber .... 2-11
3.0 SUMMARY AND DISCUSSION OF RESULTS 3-1
3.1 Results for Test Condition A: Venturi Pressure
Drop = 10.5 in. W.C 3-1
3.1.1 Particulate Matter and Radionuclide Results .... 3-1
3.1.1.1 Inlet 3-7
3.1.1.2 Outlet 3-7
3.1.1.3 Venturi Scrubber Efficiencies
Method 111 3-7
3.1.1.4 Front/Back Half Distribution of
Emissions in MM 111 Trains 3-9
3.1.2 Particle and Radionuclide Size Distribution
Data 3-11
3.1.2.1 Particle Size Distribution Data 3-11
3.1.2.2 Radionuclide Distribution Data 3-11
3.1.3 Process Samples 3-20
3.2 Results for Test Condition B: Venturi Pressure
Drop = 6.5 in. W.C 3-20
3.2.1 Outlet Particulate Matter and Radionuclide
Results 3-20
3.2.2 Estimated Venturi Scrubber Efficiencies
Method 111 (Assumed) 3-31
3.2.3 Front/Back Half Distribution of Emissions
in MM 111 Trains 3-31
JES/045 ii
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TABLE OF CONTENTS (Continued)
Section
4.0
SAMPLING AND ANALYSIS
4.1 Sampling Locations
4.1.1 Scrubber Inlet
4.1.2 Outlet Stack
4.1.3 Process Feed Sampling Location
4.2 Sampling Procedures
4.3
4.2.1 Particulate Matter and Radionuclides
Modified EPA Method 111
4.2.2 Particle Size Distribution Andersen MK III .,
4.2.3 Flue Gas Volumetric Flow Rate EPA Method 2 .,
4.2.4 Flue Gas Molecular Weight Determination
EPA Method 3
Flue Gas Moisture Content EPA Method 4
Process Feed Samples Composite Grab ,
Recovery and Analysis
Particulate Matter and Radionuclides
Particulate Size Distribution and
Radionuclides
4.3.3 Analytical Errors in Radionuclide Measurements
4.3.4 Reporting of Lead-210 Data
.5
.6
4.2
4.2
Sample
4.3.1
4.3.2
4.4 Sample Custody
Page
4-1
4-1
4-1
4-4
4-4
4-4
4-6
4-6
4-10
4-10
4-10
4-11
4-11
4-11
4-13
4-.15
4-17
4-17
5.0 QUALITY ASSURANCE AND QUALITY CONTROL (QA/QC) 5-1
5.1 Quality Assurance/Quality Control for Sampling
and Recovery
5.2 Radionuclide Analysis QA/QC
5.3 QA/QC Results for Particle Size Sampling
5.4 Mass Balance on Venturi Emission Control System
5-1
5-10
5-12
5-14
VOLUME II
APPENDIX A
APPENDIX B
APPENDIX C
C.I
C.2
C.3
C.4
C.5
EPA METHOD 111 PROTOCOL
EERF RADIOCHEMICAL ANALYSIS PROCEDURES
METHOD 111 SAMPLING PARAMETER SUMMARIES
Test Run No. 1, 8/24/88
Test Run No. 2, 8/24/88
Test Run No. 3, 8/25/88
Test Run No. 4, 8/25/88
Test Runs No. 5, 6, and 7, Outlets A and B, only.
JES/045
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TABLE OF CONTENTS (Continued)
Section
APPENDIX D
D
D
D
D
1
2
3
4
D.5
APPENDIX E
E.I
E.2
E.3
APPENDIX
F
F.I
F.2
F.3
F.4
APPENDIX G
G.
1 -
G.2
APPENDIX H
APPENDIX I
APPENDIX J
APPENDIX K
APPENDIX L
L.I
L.2
L.3
L.4
APPENDIX M
MM 111 FIELD DATA SHEETS
Test Run No. 1
Test Run No. 2
Test Run No. 3
Test Run No. 4
Test Runs No. 5, 6, and 7, Outlets A and B, only
PSD Sampling Parameter Summaries
Test Run No. 1, 8/23/88
Test Run No. 2, 8/24/88
Test Run No. 3, 8/25/88
PSD FIELD DATA SHEETS
Test Run No. 1
Test Run No. 2
Test Run No. 3
Blank PSD Runs
MOISTURE AND ORSAT ANALYSIS FIELD DATA
Moisture Recovery
Orsat
MM 111 ANALYTICAL WEIGHTS
PSD ANALYTICAL WEIGHTS
PRELIMINARY SAMPLING POINT LOCATION AND TRAVERSE DATA
SAMPLE CUSTODY LOG
RADIONUCLIDE ANALYTICAL DATA
MM 111 Radionuclide Data
PSD Radionuclide Data
Feedstock Radionuclide Data
Summary of Analytical Data
CALIBRATION DATA
JES/045
IV
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LIST OF TABLES
Table Page
1-1 Sampling and Analysis Matrix for FMC Elemental
Phosphorus Plant 1-3
1-2 Summary of the Sampling Intervals for the FMC
Test Program 1-5
1-3 Summary of Particulate Matter and Radionuclide Emission
Results: Calciner 1 Offgases, FMC-Pocatello, Idaho 1-8
1-4 Mass Collected by Stage, Venturi Pressure Drop =
10.5 in. W.C., Calciner 1 Offgases, FMC-Pocatello,
Idaho 1-10
1-5 Composite Cumulative Mass Fraction Results, Venturi Pressure
Drop = 10.5 in. W.C., Calciner 1, FMC-Pocatello,
Idaho 1-13
1-6 Composite Differential Mass Concentration, Venturi Pressure
Drop = 10.5 in. W.C., Calciner 1, FMC-Pocatello,
Idaho 1-15
1-7 Inlet Radionuclide Activity per Stage, Venturi Pressure
Drop = 10.5 in. W.C., Calciner 1, FMC-Pocatello, Idaho ... 1-16
1-8 Outlet Radionuclide Activity per Stage, Venturi Pressure
Drop = 10.5 in. W.C., Calciner 1, FMC-Pocatello, Idaho ... 1-17
1-9 Composite Cumulative Activity Fraction Results Venturi
Pressure Drop = 10.5 in. W.C., Calciner 1, FMC-Pocatello,
Idaho 1-20
2-1 Calciner Feed Rate Summary at FMC-Pocatello, Idaho 2-5
2-2 Calciner Burner Temperature Summary for FMC-Pocatello, Idaho 2-7
2-3 Fan Amperage for FMC-Pocatello, Idaho 2-9
2-4 Venturi Scrubber Water Flow Summary for FMC-Pocatello, Idaho 2-12
3-1 Summary of Particulate Matter and Radionuclide Emission
Results: Calciner 1 Offgases, FMC-Pocatello, Idaho 3-2
3-2 Summary of MM 111 Results for Run 1, Venturi Pressure
Drop = 10.5 in. W.C., Calciner 1 Offgases, FMC-Pocatello,
Idaho 3-3
JES/055
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LIST OF TABLES (Continued)
Table Page
3-3 Summary of MM 111 Results for Run 2, Venturi Pressure
Drop = 10.5 in. W.C., Calciner 1 Offgases, FMC-Pocatello,
Idaho 3-4
3-4 Summary of MM 111 Results for Run 3, Venturi Pressure
Drop = 10.5 in. W.C., Calciner 1 Offgases, FMC-Pocatello,
Idaho ... 3-5
3-5 Summary of MM 111 Results for Run 4, Venturi Pressure
Drop = 10.5 in. W.C., Calciner 1 Offgases, FMC-Pocatello,
Idaho 3-6
3-6 Venturi Scrubber Removal Efficiency for PM, Po, and Pb:
Pressure Drop = 10.5 in. W.C., Calciner 1 Offgases,
FMC-Pocatello, Idaho 3-9
3-7 Summary of Front/Back Half Distribution of Emissions:
MM 111 Sampling Trains, Pressure Drop = 10.5 in. W.C.,
Calciner 1 Offgases, FMC-Pocatello, Idaho 3-10
3-8 Cumulative Mass Fraction vs. Particle Size for
Scrubber Inlet Particulate, Venturi Pressure
Drop = 10.5 in. W.c., Calciner 1, FMC-Pocatello,
Idaho 3-14
3-9 Cumulative Mass Fraction vs. Particle Size for
Scrubber Outlet Particulate, Venturi Pressure
Drop = 10.5 in. W.c., Calciner 1, FMC-Pocatello,
Idaho 3-15
3-10 Differential Mass Concentration vs. Particle Size for
Scrubber Inlet Particulate, Venturi Pressure
Drop = 10.5 in. W.C., Calciner 1, FMC-Pocatello,
Idaho 3-18
3-11 Differential Mass Concentration vs. Particle Size for
Scrubber Outlet Particulate, Venturi Pressure
Drop = 10.5 in. W.C., Calciner 1, FMC-Pocatello,
Idaho 3-19
3-12 Cumulative Activity Fraction for Scrubber Inlet
Particulate, Venturi Pressure Drop = 10.5 in. W.C.,
Calciner 1, FMC-Pocatello, Idaho 3-25
JES/055 vi
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LIST OF TABLES (Continued)
Table Page
3-13 Cumulative Activity Fraction for Scrubber Outlet
Particulate, Venturi Pressure Drop = 10.5 in. W.C.,
Calciner 1, FMC-Pocatello, Idaho 3-26
3-14 Radionuclide Concentrations in Process Feedstock Samples
Calciner 1, FMC-Pocatello, Idaho 3-27
3-15 Summary of MM 111 Results for Run 5, Venturi Pressure
Drop = 6.5 in. W.C., Calciner 1 Offgases, FMC-Pocatello,
Idaho 3-28
3-16 Summary of MM 111 Results for Run 6, Venturi Pressure
Drop = 6.5 in. W.C., Calciner 1 Offgases, FMC-Pocatello,
Idaho 3-29
3-17 Summary of MM 111 Results for Run 7, Venturi Pressure
Drop = 6.5 in. W.C., Calciner 1 Offgases, FMC-Pocatello,
Idaho 3-30
3-18 Estimated Removal Efficiencies for PM, Po, and Pb,
Venturi Pressure Drop = 6.5 in. W.C., Calciner 1
Offgases, FMC-Pocatello, Idaho 3-32
3-19 Summary of Front/Back Half Distribution of Emissions:
MM 111 Sampling Trains, Pressure Drop = 6.5 in. W.C.,
Calciner 1 Offgases, FMC-Pocatello, Idaho 3-33
4-1 Modified Method 111 Sampling Train Components to be
Sent to EERF for Radionuclide Analysis, FMC-Pocatello,
Idaho ' 4-14
4-2 Andersen Impactor Sampling Train Components for Radionuclide
Analysis, FMC-Pocatello, Idaho 4-16
5-1 Summary of Acceptance, Criteria, Control Limits and
Corrective Action and Achieved Results 5-2
5-2 Summary of Isokinetic Results for Method 111 Sampling
Trains, FMC-Pocatello, Idaho 5-3
5-3 Summary of Isokinetic Results for Particle Sizing
Sampling Trains, FMC-Pocatello, Idaho 5-4
5-4 Summary of Leak Check Results for the Outlet
Modified Method 111 Sampling Trains, Calciner 1,
FMC-Pocatello, Idaho 5-5
JES/055 vii
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LIST OF TABLES (Continued)
Table Page
5-5 Summary of Leak Check Results for the Inlet Modified
Method 111 Sampling Trains, FMC-Pocatello, Idaho 5-6
5-6 Summary of Leak Check Results for Particle Sizing
Sampling Trains, FMC-Pocatello, Idaho 5-7
5-7 Duplicate Results for Radionuclide Analyses at
FMC-Pocatello, Idaho 5-11
5-8 Summary of MM 111 Radionuclide Field Blank Values for
the Test Program, FMC-Pocatello, Idaho 5-13
5-9 Flue Gas Interaction Sample Weight Gains,
FMC-Pocatello, Idaho 5-15
5-10 Duplicate Analyses for Lead-210 Performed by an
Independent Laboratory 5-16
JES/055 viii
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LIST OF FIGURES
Figure Page
1-1 Cumulative Mass Fractions as a Function of Particle
Size. Probability-Log Plot, Calciner 1 Offgases
FMC, Pocatello, Idaho 1-11
1-2 Differential Mass Concentration vs. Particle Size.
Calciner 1 Offgases. FMC, Pocatello, Idaho 1-14
1-3 Cumulative Polonium-210 Activity Fraction as a
Function of Particle Size, Probability-Log Plot,
Calciner 1 Offgases FMC, Pocatello, Idaho 1-18
1-4 Cumulative Lead-210 Activity Fraction as a Function
of Particle Size, Probability-Log Plot, Calciner 1
Offgases FMC, Pocatello, Idaho 1-19
2-1 Schematic of Monsanto Rotary Kiln and Pollution Control
System 2-2
3-1 Cumulative Mass Fraction as a Function of Particle Size
for Particulate at the Venturi Scrubber Inlet.
Probability-Log Plot, Calciner 1 Offgases FMC,
Pocatello, Idaho 3-12
3-2 Cumulative Mass Fraction as a Function of Particle Size
for Particulate at the Venturi Scrubber Outlet.
Probability-Log Plot, Calciner 1 Offgases, FMC,
Pocatello, Idaho 3-13
3-3 Differential Mass Concentration vs. Particle Size for
Uncontrolled Particulate. Calciner 1 Offgases.
FMC, Pocatello, Idaho 3-16
3-4 Differential Mass Concentration vs. Particle Size for
Controlled Particulate. Calciner 1 Offgases.
FMC, Pocatello, Idaho 3-17
3-5 Cumulative Polonium-210 Activity Fraction as a Function
of Particle Size for Particulate at the Venturi Scrubber
Inlet. Probability-Log Plot, Calciner 1 Offgases
FMC, Pocatello, Idaho 3-21
3-6 Cumulative Polonium-210 Activity Fraction as a Function
of Particle Size for Particulate at the Venturi Scrubber
Outlet. Probability-Log Plot, Calciner 1 Offgases
FMC, Pocatello, Idaho 3-22
JES/055 ix
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LIST OF FIGURES
Figure Page
3-7 Cumulative Lead-210 Activity Fraction as a Function
of Particle Size for Particulate at the Venturi Scrubber
Inlet. Probability-Log Plot, Calciner 1 Offgases
FMC, Pocatello, Idaho 3-23
3-8 Cumulative Lead-210 Activity Fraction as a Function
of Particle Size for Particulate at the Venturi Scrubber
Outlet. Probability-Log Plot, Calciner 1 Offgases
FMC, Pocatello, Idaho 3-24
4-1 Schematic Showing Sampling Locations at Monsanto 4-2
4-2 Schematic of the Inlet Sampling Location 4-3
4-3 Schematic Showing One of the Two Similar Outlet
Sampling Locations at FMC 4-5
4-4 Schematic of the Modified Method 111 Sampling Train 4-7
4-5 Schematic of the Andersen MK III Cascade Impactor Train 4-8
4-6 Modified Method 111 Recovery and Analysis Scheme 4-12
4-7 Example of Alphanumeric ID Codes for the FMC
Test Program 4-19
JES/045
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1.0 EXECUTIVE SUMMARY
1.1 INTRODUCTION/BACKGROUND
The Environmental Protection Agency is currently developing additional
data on the quantities of radionuclide emissions released during the
phosphate rock processing operation (calcining). The data generated during
this program will form the basis for a National Emission Standard for
Hazardous Air Pollutants (NESHAP) which will limit the quantities of
radionuclide emissions from this industry. EPA's Office of Radiation
Programs (ORP) and Office of Air Quality Planning and Standards (OAQPS) are
jointly participating in this regulatory effort.
Emission tests at two elemental phosphorus plants were performed for
this program. The results from the second of these tests, which was
conducted at the FMC, Pocatello, Idaho, plant are the subject of this
report. The results of the first site test, which was conducted at Monsanto
in Soda Springs, Idaho, is reported separately (88-EPP-01).
Since the radionuclides in the offgas streams are associated with the
particulate matter, emission testing procedures involved collection of PM
from these streams and subsequent analyses of these samples for their
radionuclide content. The emissions that are being studied include
particulate matter (PM), particulate size distribution (PSD) and two
particular radionuclides: Polonium-210 (Po-210) and lead-210 (Pb-210).
1.1.1 Test Program Objectives
The purpose of this document is to present the results from the August
test program at the FMC phosphorus plant in Pocatello, Idaho. The focus of
this report is on the presentation of measured emissions. No attempt is
made to perform rigorous analyses of these data such as are commonly
performed in support of NESHAP development. The Industrial Studies Branch
(ISB) and their contractors will analyze the data generated during this test
program to develop the specific information needed to support the
JES/045 1-1
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regulatory development. The primary objectives of the FMC test program
were:
o to quantify the particulate matter, polonium-210, and lead-210
emission rates in the calciner offgases at both the inlet and
outlet venturi scrubber sampling locations, and
o to determine the distribution of particulate matter, polonium-210,
and lead-210 by particle size in the offgases at both inlet and
outlet locations.
These pollutants were quantified at two venturi pressure drops: the maximum
operable (10.5 in. W.C.) and the typical (6.5 in. W.C.). The outlet stacks
were sampled at both pressure drops. The inlet location was sampled only
during the first test condition since the uncontrolled flue gas is not
affected by the venturi scrubber and the calciner operating conditions were
equivalent. In addition, grab samples were collected to quantify the
concentration of polonium-210 and lead-210 in the calciner feedstock.
1.1.2 Overview of Testing Activities
On-site activities began on August 22 and were completed on August 27,
1988. The sampling and analysis matrix as planned and presented in the
project test plan is included in Table 1-1. During the test program, slight
deviations from the planned approach were made to compensate for sampling
difficulties encountered during the first and second day of testing. These
difficulties and the corrective actions taken are discussed in detail in
Sections 3.0 and 4.0 of this document.
During runs 1-4, samples were collected simultaneously at both the
venturi scrubber inlet and each of the plant's two stack outlet locations.
Thus, for each run, three samples were collected; one at the inlet and one
at each of the two outlet stacks. During runs 5-7, samples were collected
only at each of the two outlet stacks.
The sampling intervals are summarized for each test run in Table 1-2.
In order to collect at least two MM 111 samples at each location that met
isokinetic QA requirements, an additional test run was conducted. An
JES/045 1-2
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C_ TABLE 1-1. SAMPLING AND ANALYSIS MATRIX FOR FMC ELEMENTAL PHOSPHOROUS PLANT
m
o
01 Sampling Lpcation/
Conditions Sampling Method
Scrubber Inlet Modified Method 111*
- Operating
Condition A Andersen Impactor
Outlet Stack #1-1 Modified Method 111"
- Operating
Condition A Andersen Impactor
Outlet Stack #1-2 Modified Method 111*
- Operating
i Condition A Andersen Impactor
CO
Outlet Stack #1-1 Modified Method 111*
- Operating
Condition B8
Outlet Stack #1-2 Modified Method 111*
- Operating
Condition B8
Target Emission
or Stack Parameter
Particulate
Radionuclides
Particulate size
Radionuclides
Particulate
Radionuclides
Particulate size
Radionuclides
Particulate
Radionuclides
Particulate size
Radionuclides
Particulate
Radionuclides
Particulate
Radionuclides
Analytical
Method
Gravimetric
alpha spec.
Gravimetric
alpha spec.
Gravimetric
alpha spec .
Gravimetric
alpha spec.
Gravimetric
alpha spec.
Gravimetric
alpha spec.
Gravimetric
alpha spec.
Gravimetric
alpha spec.
Number of Number of
Number of Sample Fractions Radlonucllde
Test Runs Per Test Run Samples
3 2 (front/back)C 6
3 6d 18
3 2 (front/back)0 6
3 6d 18
3 2 (front /back)0 6
3 6d 18
3 2 (front/back)C 6
3 2 (front/back)0 6
Process Feed
- Operating
Conditions A i B
Grab
Radionuclides
Alpha spec.
Field Blanks
Modified Method 111
Andersen Impactor
Particulate
Radionuclides
Particulate size
Radionuclides
Gravimetric
alpha spec.
Gravimetric
alpha spec.
2 (front/back)
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TABLE 1-1. SAMPLING AND ANALYSIS MATRIX FOR FMC ELEMENTAL PHOSPHOROUS PLANT (Continued)
Sampling Location/
Conditions Sampling Method
Target Emission
or Stack Parameter
Analytical
Method
Number of
Test Runs
Numbe c of
Sample Fractions
Per Test Run
Number of
Radionuclide
Samples
Reagent Blanks
Modified Method 111
Filters, Acetone,
Nitric Acid
Andersen Impactor
Filters
Radionuclides
Radlonuclide s
Alpha spec.
Alpha spec.
NA
NA
NA
NA
TOTAL
103
Impinger solutions of the Method 111 train were nitric acid.
Target radionuclides included Polonium-210 and Lead-210.
CFront half consisted of filter and probe and nozzle rinses, back half consisted of impinger contents and rinses.
Andersen impactor stages were combined into 5 fractions as follows: No. 1 - precutter stages 0 and 1; No. 2 - stages 2, 3, 4, and 5j
No. 3 - stage 6; No. 4 - stage 7; and No. 5 - stage 8.
6Reagent blanks (filters and solvents) were collected and archived. Radionuclide analysis could be performed on these samples in the event
that field blanks show contamination.
Condition A: normal production rate (80-100 percent capacity) and venturi scrubber Ap = 10 in. H2O.
Condition B: normal production rate (80-100 percent capacity) and venturi scrubber AP = 6-5 ln- H2°-
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m
oo
o
-u
en
Date
TABLE 1-2. SUMMARY OF THE SAMPLING INTERVALS FOR THE FMC TEST PROGRAM (August 1988)
(24-hour clock)
Test
Condition
Run
Inlet
Outlet A
Outlet B
Comments
Method 111
8/24/88
8/24/88
8/25/88
8/25/88
8/26/88
8/26/88
8/26/88
09:50-11:46
16:26-18:16
11:30-13:20
17:30-19:26
B
09:42-11:31 11:00-12:15 The inlet train did not meet iso-
klnetic requirements.
16:21-17:33 16:20-17:30 The Inlet train did not meet iso-
kinetic QA requirements.
11:22-12:32 11:25-12:33
17:22-18:34 17:20-18:25
08:30-10:39 09:43-10:48
12:38-13:48 12:35-13:40
15:50-16:59 15:50-16:54
Particle Sizing
8/23/88 A
8/24/88 A
8/25/88 A
8/25/88
8/25/88
12:17-12:21
13:32-13:36
14:33-14:37
Blank 08:34-08:38
11:50-13:05 11:40-13:22
12:53-14:08 13:21-14:51
14:06-15:21 14:10-15:40
19:30-21:00
08:40-10:10
Substrates wet on outlet B train.
Outlet B train invalidated.
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additional outlet B PSD sample was collected after run 3 when the substrate
was determined to be wet and the outlet B run 3 PSD sample was invalidated.
The inlet and outlet particle size samples were collected simultaneously
using in-stack Andersen impactors.
Particulate emissions and associated radionuclides were collected from
the streams using a modification of EPA Method 111. The specific sampling
portion of Method 111 is identical to those procedures described in EPA
Method 5.
The modifications made to the Method 111 train for this program
included using 0.1 N nitric acid for impinger solutions instead of water,
and recovery and analysis of all sampling train fractions. The purpose of
the nitric acid impinger solutions was to minimize surface effects that
might inhibit recovery of radionuclides and metals from sampling train
glassware.
The purpose for analyzing all train components was to quantify total
radionuclide content of the offgas streams. The MM 111 sampling trains were
recovered in two fractions (front and back halves). The front half
consisted of the filter and rinses from the probe, nozzle and filter holder;
whereas, the back half consisted of the impinger contents and rinses. Both
front and back half sample fractions were analyzed separately by EPA's
Eastern Environmental Radiation Facility (EERF) for radionuclide content.
Particle sizing samples were collected using heated Andersen MK-III
in-stack cascade impactors and were collected during test condition A only.
Particle size operating parameters were selected to optimize the separation
of the fine particulate fraction (less than 2 microns). Particle size
distributions were determined for each of the nine inlet and outlet samples.
For the radioactivity analyses, stages 2 through 5 were combined into one
sample for analysis. Stages 1, 6, 7, 8 and the backup filter were each
analyzed individually.
Process feed samples were collected during the testing and composited
to determine the activity in the feedstock briquettes. Field blanks and
reagent blanks were collected during the FMC test program and are presented
and discussed in the Quality Assurance/Quality Control (QA/QC) section of
this document.
JES/045 1-6
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Due to the low concentration of lead-210 in the sample aliquots
analyzed, the precision of the lead-210 measurements was fairly low and was
estimated at 50 percent at the 95 percent confidence interval. For the
polonium-210 measurements, there is a high degree of confidence in the data.
The analytical precision in the polonium-210 measurement was less than 10
percent at the 95 percent confidence level.
1.2 SUMMARY OF EMISSION RESULTS
1.2.1 PM and Radionuclides (MM 111)
Emission testing was performed while operating the process at
two different test conditions. At test condition A, the venturi scrubber
pressure drop was set at 10.5 inches water column. At test condition B, the
pressure drop across the venturi scrubber was set at 6.5 inches water
column.
Table 1-3 contains a summary of the particulate and radionuclide
emissions measured during the program. As seen in the table, particulate
matter concentrations at the inlet for the two valid test runs (runs 3
and 4) averaged 1,088 mg/dscm (0.4755 gr/dscf). The outlet particulate
matter concentration during condition A averaged 94.76 mg/dscm
(0.04142 gr/dscf). During condition B, the outlet particulate matter
concentration averaged 81.50 mg/dscm (0.03562 gr/dscf). On a mass emission
rate basis, particulate matter emission rates at the inlet averaged
245.9 kg/hr (540.8 Ibs/hr). At the outlet, the particulate emission rates
averaged 20.75 kg/hr (45.75 Ibs/hr) at test condition A and 21.93 kg/hr
(48.34 Ib/hr) at test condition B. The outlet particulate matter emission
rate represent the emission rate for calciner #1, which has two stacks.
Polonium-210 (Po-210) and lead-210 (Pb-210) concentrations in the inlet
stream averaged 4,755 and 195.0 pCi/dscm (134.7 and 5.526 pCi/dscf),
respectively, for the two valid test runs. The concentration of Po-210 and
Pb-210 in the outlet streams at test condition A averaged 4,895 and
118.8 pCi/dscm (138.6 and 3.336 pCi/dscf), respectively. At test
condition B, the concentrations of Po-210 and Pb-210 in the outlet streams
JES/045 1-7
-------
TABLE 1-3. SUMMARY OF PARTICULATE HATTER AND RADIONUCLIDE EMISSION RESULTS: CALCINER 1 OFFGASES, FMC-POCATELLO, IDAHO (August 1988)
Particulate Matter
Run Concentration
Location
Inlet
b
Outlet
(Scrubber
AP = 10.
in. W.C.
Outlet
(Scrubber
Ap = 6.5
in. W.C.
Number (gr/dscf)
1 0.3849
2 0.4983
3 0.4549
4 0.4962
Average 0.4755
(Runs 3-4)
1 0.03918
5 2 0.04584
)
3 0.04120
4 0.03944
Average 0.04142
(Runs 1-4)
5 0.03362
6 0.03776
)
7 0.03548
Average 0.03562
(Runs 5-7)
Polonium-210 Lead-210
Emission Emission
Mass Rate Concentration Rate Activity: PM Concentration Rate Activity: PM
(mg/dscm) (Ib/hr) (kg/hr) (pCi/dscf)
880.8
1140
1041
1135
1088
89.64
104.9
94.28
90.24
94.76
76.93
86.40
81.18
81.50
Outlet Mass
Emission
Rate (Ib/yr,
461.2 209.2 166.5
617.0 279.9 173.9
527.7 240.6 143.7
553.9 251.3 125.7
540.8 245.9 134.7
41.46 18.81 166.5
49.76 22.57 168.8
46.57 21.12 123.6
45.21 20.51 95.63
45.75 20.75 138.6
45.88 20.81 108.7
50.68 22.99 144.2
48.46 21.98 128.7
48.34 21.93 127.2
141 tons/yr
(pCi/dscm) (uCi/hr) (nCi/g PM) (pCi/dscf) (pCi/dscro) (uCi/hr) (nCi/g PM)
5880 1397 6.676 3.361 118.7 28.19 0.1347
6140 1507 5.385 2.274 80.27 19.71 0.0704
5074 1167 4.875 2.834 100.1 23.01 0.0961
4433 982.0 3.907 8.217 290.0 64.22 0.2555
4755 1075 4.391 5.526 195.0 43.62 0.1758
5880 1234 64.75 1.233 43.53 9.134 0.4706
5958 1283 55.78 2.486 87.78 18.90 0.8655
4365 978.0 46.95 8.596 303.5 68.00 3.429
3377 767.4 37.40 1.027 36.27 8.244 0.4012
4895 1065 51.22 3.336 118.8 26.07 1.291
3840 1039 49.83 0.8112 28.64 7.749 0.3947
C C C C
5093 1355 60.11 7.965E-05 2.813E-03 7.483E-04 2.978E-05
C C C C
4544 1230 55.92 0.4656 16.44 4.451 0.2036
4492 1208 55.29 0.4256 15.03 4.067 0.1995
7.05 Ci/yr 0.0237 Ci/yr
AP = 6.5
in W.C.)
Average inlet values from runs 3 and 4.
Outlet concentration values for each run are the averages of the two outlet locations weighted for the different stack gas flow rates. The mass rates
are the sum of the mass rates for the two outlet locations.
°Lead-210 was not detected in either the Outlet A or Outlet B samples. The values presented are an average minimum detection lijnit.
-------
averaged 4,492 and 15.03 pCi/dscm (127.2 and 0.4256 pCi/dscf), respectively.
On an emission rate basis, Po-210 and Pb-210 emissions at the inlet averaged
1,075 and 43.62 uCi/hr. At the outlet, the emission rates for Po-210 and
Pb-210 at condition A averaged 1,065 and 26.07 uCi/hr and at condition B
averaged 1,208 and 4.067 uCi/hr, respectively. For several of the test
runs, the Pb-210 concentrations were below minimum detection limits and for
many of the test runs, the Pb-210 concentrations were within ten times the
minimum detection limit. Thus, although the Pb-210 concentrations for
condition B appear to be lower than for condition A, these concentrations
are actually near minimum detection limits in both cases and may be
considered to agree within analytical precision.
1.2.2 Particulate Size Distribution
Particle size analysis quantifies the particulate mass in a given size
range. The mass collected on each stage are presented for each run in
Table 1-4. For a given location, the data show consistency between test
runs.
The particle size results are presented in two ways in this report.
The first is a plot of the cumulative mass fraction versus the interval
endpoint (Dpc0) as shown in Figure 1-1. Dp50 represents the effective stage
cut diameter calculated for the specified sampling run. Ideally, each
impactor stage collects all particles having an aerodynamic diameter greater
than the stage cut diameter (Dp50). In reality, the effective stage cut
diameter (Dp50) is assumed to be equal to the particle diameter for which
the stage collection efficiency is 50 percent. The stage cut diameter is
calculated from the sampling run conditions, the physical dimensions of the
impactor, and a theoretical calibration value (Stokes number). This curve
is used to estimate the fraction of the particulate less than a specific
particle diameter.
For the inlet location, 30 percent of the particulate mass is composed
of particles that are less than 0.5 microns in diameter. For the outlet
locations, 80 percent of the particulate mass comprises particles that are
less than 0.5 microns in diameter. The particulate mass at the inlet
JES/045 1-9
-------
TABLE 1-4. MASS COLLECTED BY STAGE, VENTURI PRESSURE DROP = 10.5 In. W.C., CALCINER 1 OFFGASES, FMC-POCATELLO, IDAHO (August 1988)
Stage Run 1
1* 0.03190
2 0.00080
3 0.00099
4 0.00460
5 0.00028
6 0.00128
7 0.00014
8 0.00040
Back-up 0.00106
Total 0.04145
Inlet
Run 2
0.03240
0.00103
0.00094
0.00069
0.00052
0.00038
0.00011
0.00019
0.00149
0.03775
Mass Collected per stage (grains per sample)
Outlet A
Run 3
0
0
0
0
0.
0
0.
0.
0,
0.
.04549
.00129
.00115
.00035
.00023
.00030
.00000
,00000
,00116
.04997
Run 1
0
0
0
0
0
0
0
0
0
0
.00060
.00037
.00113
.00015
.00191
.00264
.00340
.00744
.06493
.08257
Run 2
0.
0
0
0
0
0.
0,
0
0
0
,00100
.00056
.00076
.00103
.00107
.00156
.00214
.00337
.04316
.05465
Run 3 Run 1
0.00062 0.00170
0.00054 0.00121
0.00072 0.00140
0.00069 0.00139
0.00138 0.00184
0.00187 0.00168
0.00349 0.00276
0.01252 0.00447
0.04888 0.05845
0.07071 0.07490
Outlet B
Run 2
0.00100
0.00070
0.00092
0.00088
0.00164
0 . 00221
0.00252
0.00598
0.05827
0.07412
Run 3
0.00066
0.00027
0.00052
0.00091
0.00130
0.00196
0.00519
0.01309
0.05131
0.07521
Stage 1 includes the pre-impactor stage.
-------
CD
-C
CO
CO
I s
o
(0
k_ o
LL S
CO
CO o
CD •"
1 '
3
O
0.1
i
sE
f
OUTLET
INLET
m
O- -W « -O —
1.0
(microns)
10
O- ^J » -O —
100
Figure
1 -1. Composite curves of mass fractions as a function of particle size
Probability-Log plot, Calciner 1 offgases.
FMC, Pocatello, Idaho (August 1988).
JES/045
1-11
-------
consists of approximately 13 percent PM1Q (i.e., participate matter less
than 10 microns in diameter). At the outlet, PM1Q accounts for about
98.4 percent of the particulate mass. The cumulative mass fraction data are
presented in tabular form in Table 1-5.
The second presentation method is to plot differential mass
concentration versus the particle geometric mean diameter as shown in
Figure 1-2. The differential mass concentration is the particulate
concentration in the flue gas normalized per unit of particle size. This
curve is used to estimate the particulate concentration in the flue gas for
a specific particle size interval.
For the inlet location, the differential mass concentration ranged from
0.0650 gr/dscf for 7.5 to 50 micron particles to 0.0040 gr/dscf for 0.7 to
2.0 micron particles. The majority (87%) of the uncontrolled particulate is
above 10 microns.
For the outlet location, the differential mass concentration ranged
from 0.0015 gr/dscf for 7.5 to 50 micron particles to 0.0190 gr/dscf for
0.1 to 0.7 micron particles. The majority (80%) of the controlled
particulate is below 0.5 microns.
Figure 1-2 also provides an indication of venturi scrubber removal
efficiency by particle size fraction. The data used to prepare these curves
are presented in Table 1-6.
Radionuclide activity was measured for the samples collected from the
inlet and outlet. For each test run, stages 2 through 5 were combined into
one sample for analysis. Stages 1, 6, 7, 8 and the backup filter were each
analyzed individually. The activity results are summarized as pico Curies
per sample in Tables 1-7 and 1-8.
In order to evaluate the radionuclide data, the cumulative activity
fraction was plotted against the interval endpoint (Dp5Q) determined from
the PSD run. The cumulative activity fraction is plotted in Figure 1-3 for
polonium-210 and in Figure 1-4 for lead-210. The data plotted in these
figures are summarized in Table 1-9.
These data indicate that the radioactivity is associated with small
particles. Controlled particles less than 1 micron contained 82 percent of
the radioactivity for Po-210 and 70 percent of the radioactivity for Pb-210.
JES/045 1-12
-------
TABLE 1-5. COMPOSITE CUMULATIVE MASS FRACTION RESULTS,
VENTURI PRESSURE DROP = 10.5 in. W.C., CALCINER 1,
FMC-POCATELLO, IDAHO (August 1988)
Interval3
EnjJP°int Mass Fraction Less Than (%)
Up50
(microns) Inlet Outlet
0.5 3 80
1 4 88
2.5 7 95
5 10 97
10 13 98.4
= the theoretical stage endpoint (interval endpoint) is the
aerodynamic diameter of the smallest particles collected on a stage
with an efficiency of 50 percent.
JES/045 1-13
-------
o 10 "'-
O 10 "2-
CD
O
T3 10
10
Inlet
Outlet
n r
0.01
-|—r i i i i r
0.1 1 10
Aerodynamic Particle Diameter (um)
Figure 1-2. Composite curves of differential mass concentration as a
function of particle size. Calciner 1 offgases.
FMC, Pocatello, Idaho (August 1988)
1-14
-------
TABLE 1-6. COMPOSITE DIFFERENTIAL MASS CONCENTRATION,
VENTURI PRESSURE DROP = 10.5 in. W.C., CALCINER 1,
FMC-POCATELLO, IDAHO (August 1988)
Geometric
Mean
(microns)
Interval
range
(microns)
Differential Mass Concentration (qr/dscf)
Inlet Outlet
0.5
1
2.5
5
10
0.1-0.7
0.7-2.0
2.0-3.5
3.5-7.5
7.5-5.0
0.0013
0.0040
0.0200
0.0500
0.0650
0.0190
0.0050
0.0030
0.0020
0.0015
JES/045
1-15
-------
TABLE 1-7. INLET RADIONUCLIDE ACTIVITY PER STAGE, VENTURI PRESSURE DROP = 10.5 in. W.C., CALCINER 1
FMC-POCATELLO, IDAHO (August 1988)a
Stage
Inlet - Run 1
Radioactivity per stage (pico Curies per sample)
Inlet - Run 2
Po-210
Pb-210
Po-210
Pb-210
Inlet - Run 3
Po-210
Pb-210
11.955
0.878
10.17
1.439
35.02
2.978
2-5
17.532
1.774
18.19
3.580
64.76
KD [1.336]
8.684
9.147
ND [0.781]
ND
7.899
11.01
ND [0.712]
ND [1.219]
12.83
10.896
0.8781
1.681
10.250
ND
13.94
1.978
13.262
ND [0.453]
Back-up
112.560
ND
82.64
3.284
147.04
3.1088
Total
170.128
3.433
143.8
12.21
77.58
2.214
The data should be considered significant to three figures.
ND = Not detected. Value in brackets is the minimum detection limit. When no value is presented in brackets, the minimum detection limit
was essentially zero.
-------
TABLE 1-8. OUTLET RADIONUCLIDE ACTIVITY PER STAGE, VENTURI PRESSURE DROP = 10.5 In. W.C., CALCINER 1
FMC-POCATELLO, IDAHO (August 1988)a
Outlet A - Run 1 Outlet A - Run 2
Stage Po-210 Pb-210 Po-210 Pb-210
1 101.5 ND [0.5158] 96.03 ND [0.9248]
2-5 275.0 2.670 327.5 ND [3.317]
6 87.05 16.75 88.98 ND [0.7925]
7 150.56 3.0656 122.2 ND [0.9781]
8 256.7 ND 122.2 2.297
Back-up 1999 ND [13.36] 1942 ND [9.788]
Total 2830 201.9 2699 18.10
Radioactivity
Outlet A
Po-210
21.66
112.6
51.58
121.7
345.9
per stage
- Run 3
Pb-210
1.985
2.304
2.137
2.370
4.997
2115 ND [13.67]
2769
27.46
(pico Curies
Outlet B
Po-210
63.26
199.0
44.17
91.60
201.8
2590
3190
per sample)
- Run 1 Outlet B - Run 2
Pb-210 Po-210 Pb-210
ND 101.3 ND
2.579 335.2 ND [0.2253]
ND [0.3147] 120.7 ND [0.6223]
2.592 215.9 27.92
6.429 472.7 10.66
ND [3.894] 4222 105.7
15.81 5468 145.2
Outlet B - Run 3
Po-210 Pb-210
77.10 ND
240.7 ND
90.21 ND [0.1105]
269.2 ND
728.7 6.557
2566 ND
3972 6.668
The should be considered significant to three figures.
ND = Not detected. Value in brackets is the minimum detection limit. When no value is presented in brackets, the minimum detection limit was
essentially zero.
-------
0.1
100
Figure 1 -3. Composite curves of cumulative Polonium-210 activity fraction as a
function of particle size, Probability-Log plot, Calciner 1 offgases.
FMC, Pocatello, Idaho (August 1988).
JES/045
1-18
-------
Ł 8
H
co
c
o
O
to
CN
o
0.1
i
-jff-
-OUTLET'
1.0
(microns)
10
100
Figure 1 -4. Composite curves of cumulative Lead-210 activity fraction as a
function of particle size, Probability-Log plot, Calciner 1 offgases.
FMC, Pocatello, Idaho (August).
JES/045
1-19
-------
TABLE 1-9. COMPOSITE CUMULATIVE ACTIVITY FRACTION RESULTS,
VENTURI PRESSURE DROP - 10.5 in. W.C., CALCINER 1,
FMC-POCATELLO, IDAHO (August 1988)
Interval a
Endpoint
(microns)
0.5
1
2.5
5
10
Mass Fraction
Po-210
Inlet Outlet
64 72
74 82
84 90
89 95
93 97
Less Than (%)
Pb-210
Inlet Outlet
30 54
46 70
64 87
78 94
87 98
Dp5Q = the theoretical stage endpoint (interval endpoint) is the
aerodynamic diameter of the smallest particles collected on a stage
with an efficiency of 50 percent.
JES/045
1-20
-------
Particles less than 0.5 micron contained 72 percent of Po-210 and 54 percent
of Pb-210 radioactivity.
The curves presented in this section were fitted to the test run data
presented in Section 3.0. Thus, these curves are a composite representing
the typical characteristics of the particulate.
1.3 TEST REPORT ORGANIZATION
This emission test report is presented in two volumes. Information
presented in this document (Volume I) is organized as follows: Section 2.0
contains a brief description of the calcining process and the air pollution
control systems at the plant; Section 3.0 presents a summary and discussion
of the results; Section 4.0 describes the specific sampling locations and
the sampling and analysis procedures that were used; and Section 5.0
describes the specific quality assurance and quality control measures that
were taken to ensure useful and valid data.
The supporting data for the results presented in this volume are
included in Volume II as appendices. Volume II contains sampling and
analytical protocols, all field and lab data sheets, data reduction
summaries, and calibration data.
JES/045 1-21
-------
2.0 DESCRIPTION OF PROCESS AND AIR POLLUTION CONTROL SYSTEMS
2.1 PROCESS DESCRIPTION
The FMC, Pocatello, Idaho, plant produces elemental phosphorus from
phosphate ore (shale). The calcining process, which is the focus of this
emission study, is discussed in more detail in the following paragraphs.
Phosphate rock is crushed, screened, and formed into briquettes, before
being fed into the calciner. The phosphate rock is heated to remove organic
material and to form heat-hardened nodules that withstand further processing
without disintegrating. The nodules are cooled and passed through a
proportioning building, where they are blended with sized coke and silica
into a material called the burden, which is fed into an electric-arc
reducing furnace. High temperature reactions in the furnace drive off
gaseous phosphorus and carbon monoxide and leave molten residues of slag and
ferrophosphorus. The furnace offgases pass through electrostatic precipi-
tators to remove dust before entering a condenser, where the phosphorus is
condensed, collected in a sump, and pumped to storage. The carbon monoxide
is fed to the calciner as fuel.
The FMC facility has two moving-grate calciners, designated as Unit 1
and Unit 2. A simple schematic overview of the process, showing feed and
offgas streams around each of the calcining units is shown in Figure 2-1.
Prior to entering the calciner, the ore is formed into briquettes using a
mechanical process. These briquettes are fed by a vibratory feeder onto the
pallets of the calciner grate. The calciner is divided into three sections.
The first section, the calcining section, has six overflow burners that heat
the bed. Carbon monoxide (CO) from the electric furnace exhaust gas streams
is the primary fuel, with natural gas as an auxiliary fuel source. The
second section is a cooling section that is open to the atmosphere. The
down-draft air from this section is drawn through a fan and used as
combustion air in the CO burners. The final section is a cooling section.
The cooling air is drawn down through the bed and exhausted out a stack.
JES/045 2-1
-------
m
oo
o
-p»
en
ro
i
ro
Ore
Feed
F
Ore
Feed
F
— Fuel
\ <
Calciner No. 1
I
T
Product to
Deducing Furnace
— Fuel
• '
Calciner No. 2
i
t
Product to
Deducing Furnace
Offgases
Offgases "~
^ ^x
N/Gnturi
Mr* 1 1
X^ ^
•
No. 1-2
\sr ^\
No. 2-1
s^ ^s
sS' ^^
Dernister
Fan
f >v
' ^VNo. 1-27
I.D. \^ -S
Fan
* in *" \No.2-y
I.U. N>^ ^
Fan
S >v
. | 1 St1*'6!? 1
**• *\No. 2-2/
I.D. ^~~*/s
Calciner #2
and associated
is not currently
in operation.
Projected
operation date:
October 1988.
No. 2-2
Fan
cc
-------
The cooled nodules are discharged through a hopper to a conveyor belt and
transported to the furnace area.
2.2 AIR POLLUTION CONTROL EQUIPMENT (CALCINING OPERATION)
The offgases are vented to separate pollution control systems. As seen
in the figure, offgases enter a common inlet and are split into two parallel
streams, each containing a venturi scrubber, a demister, and an induction
fan. After passing through their respective ID fans, the exhaust gases from
each calcining unit are discharged through two similar 22.9 m (75 ft) tall
stacks. These outlet stacks were scheduled to be rebuilt in October of
1988. The height of each of the rebuilt stacks is expected to be
approximately 30.5 m (100 ft.).
2.3 PROCESS AND POLLUTION CONTROL DATA
The emission test program at FMC was performed during two periods of
different scrubber operating conditions, Ap = 10.5 in. and Ap = 6.5 in. of
HpO. Process conditions for each set of tests were within "normal"
operating ranges. Operational ranges for process parameters were
established by ISB and FMC personnel prior to testing based on historical
plant data and full production capacity. Key parameters were monitored
throughout the testing period by FMC's automated data acquisition system.
Additionally, Radian personnel periodically monitored these data from the
plant's control room for the purpose of coordinating sample collection
activities with process/control device conditions. Key parameters monitored
and reported for this test program are, with a few additions, the same as
those measurements monitored during the November 1983 test program at FMC.
The averages for the emission testing period (August 23-26) represent
the average of instantaneous values recorded by Radian personnel during each
test period. The average values presented are not intended to represent
daily averages. The intention is to indicate consistent and normal plant
operation during the emission testing. The key operating parameters
monitored during the emission test period are discussed below and data which
has been claimed confidential by the facility have been indicated.
JES/045 2-3
-------
2.3.1 Process Rate
The process rate was monitored in the control room in terms of calciner
speed. The "normal" range for calciner speed was reported to be [claimed
confidential] meters per minute (m/min also equivalent to [claimed
confidential] feet per minute [ft/min]). Table 2-1 is a summary of the
process rate information recorded by Radian personnel during the test
period. A plant supplied conversion chart in the control room was used to
convert the calciner speed to a process rate based upon the bed depth. A
bed depth of [claimed confidential] inches was maintained throughout the
test period. Calciner grate speed was controlled manually by an operator
who watches the feed unit through a window. Calciner grate speed varied due
to availability of feed material and burner temperature during the testing.
Calciner grate speed was calculated upon the pallet count per elapsed time.
The grate speed recorded during short time periods had a greater variability
than reported previously.
2.3.2 Burner Temperatures
The burner temperatures appeared on a digital readout in the control
room. All six burner temperatures were monitored for Unit No. 1. During
testing operations, burner temperatures were within normal operating range.
Burner temperatures recorded during the emissions testing are summarized in
Table 2-2.
2.3.3 Fan Amperage
Amperage for the calciner cooling and scrubber ID fans were monitored
during the test period as a relative indicator of calciner exhaust air.
The fan amperage is summarized in Table 2-3. The fan amperage values
recorded during the test period are within the expected range, with the
exception of scrubber 1-1 induced draft fan on August 24th, during MM 111
test runs 1 and 2. The fan amperage during this period was 10-15 percent
lower, which resulted from the insert being raised too far in the variable
throat venturi for the scrubber 1-1 train. The resultant scrubber pressure
JES/045 2-4
-------
TABLE 2-1. CALCINER FEED RATE SUMMARY AT FMC-POCATELLO, IDAHO (August 1988)
Date
8/23/88
8/23/88
8/23/88
8/23/88
8/23/88
8/23/88
8/23/88
Time
11:23
12:23
12:38
12:50
13:02
13:17
16:00
Grate
Speed
Pallet
(counts)
Elapsed
Time
(min)
Feed
Rate
(tons/hr)
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
09:44
10:00
11:10
11:52
12:39
13:14
14:18
14:45
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
16:48
17:27
17:42
18:06
18:20
18:30
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
11:30
11:45
12:05
13:12
14:00
14:15
14:30
15:00
15:15
15:30
15:45
16:00
17:20
18:00
18:20
18:35
18:50
19:05
19:20
19:35
19:50
20:05
20:20
20:35
[CLAIMED CONFIDENTIAL]
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
08:15
08:30
09:15
09:30
09:45
10:00
10:15
10:30
10:45
2-5
-------
TABLE 2-1. (Continued)
Date
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
Time
Grate
Speed
Pallet
(counts)
Elapsed
Time
(m i n)
Feed
Rate
(tons/hr)
12:15
12:30
12:45
13:00
13:15
13:30
13:45
15:50
16:00
16:15
16:30
16:45
17:00
[CLAIMED CONFIDENTIAL]
2-6
-------
TABLE 2-2. CALCINER BURNER TEMPERATURE SUMMARY FOR FMC-POCATELLO, IDAHO (AUGUST 1988)
Date
Time
Average
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
Average
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
09:30
09:45
10:00
11:08
11:50
12:38
13:11
13:50
14:16
14:44
16:15
16:45
17:20
17:40
18:00
18:18
18:30
11:24
11:45
12:00
12:30
12:45
13:11
14:00
14:15
14:30
15:00
15:15
15:30
15:45
16:00
17:20
17:46
18:00
18:20
18:35
18:50
19:05
19:20
19:35
19:50
20:05
20:20
20:35
20:50
Burner Temperature (deg. F)
#1
#2
#3
#4
#5
Windbox
#13 Temp
(deg. F)
8/23/88
8/23/88
8/23/88
8/23/88
8/23/88
8/23/88
8/23/88
8/23/88
8/23/88
8/23/88
8/23/88
8/23/88
8/23/88
8/23/88
08:00
09:00
10:00
10:36
11:00
11:15
12:00
12:30
12:45
13:00
13:15
14:00
15:15
16:00
[CLAIMED CONFIDENTIAL]
Average
2-7
-------
TABLE 2-2. (Continued)
Date
Time
Burner Temperature (deg. F)
#2
Uindbox
#13 Temp
(deg. F)
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
Average
08:15
08:30
09:15
09:30
09:45
10:00
10:15
10:30
10:45
12:15
12:30
12:45
13:00
13:15
13:30
13:45
14:00
15:50
16:00
16:15
16:30
16:45
17:00
[CLAIMED CONFIDENTIAL]
2-8
-------
TABLE 2-3. FAN AMPERAGE FOR FMC-POCATELLO, IDAHO (August 1988)
Date
8/23/88
8/23/88
8/23/88
8/23/88
8/23/88
8/23/88
8/23/88
8/23/88
8/23/88
8/23/88
8/23/88
8/23/88
8/23/88
8/23/88
Time
08:00
09:00
10:00
10:36
11 :00
11:15
12:00
12:30
12:45
13:00
13:15
14:00
15:15
16:00
Primary
Cooling Fan
(amps)
520
460
500
500
500
500
500
500
500
500
500
520
480
NR
ID Fan (amps)
#1-1
NR
NR
NR
452
457
449
454
444
451
454
445
NR
453
445
#1-2
NR
NR
NR
458
462
461
462
448
459
462
450
NR
458
456
Average
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
09:30
09:45
10:00
11:08
11 :50
12:38
13:11
13:50
14:16
14:44
16:15
16:45
17:20
17:40
18:00
18:18
18:30
Average
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
Average
11:24
11:45
12:00
12:30
12:45
13:11
14:00
14:15
14:30
15:00
15:15
15:30
15:45
16:00
17:20
17:46
18:00
18:20
18:35
18:50
19:05
19:20
19:35
19:50
20:05
20:20
20:35
20:50
498
460
480
460
500
500
500
500
460
500
500
480
480
480
480
500
490
490
486
490
490
NR
490
495
490
495
490
490
485
485
485
480
480
480
480
445
445
445
445
450
445
450
450
150
150
445
NR
447
450
424
415
417
409
411
405
411
413
409
409
411
411
413
404
401
403
407
410
445
444
451
447
NR
NR
NR
NR
444
NR
NR
NR
NR
444
456
445
NR
456
449
454
445
454
447
459
451
464
446
457
450
458
470
468
465
464
454
454
460
456
457
457
458
464
461
457
451
450
456
459
449
448
447
456
NR
NR
NR
NR
449
NR
NR
NR
NR
455
448
452
NR
453
454
451
458
452
458
458
456
450
454
453
453
2-9
-------
TABLE 2-3. (Continued)
Date
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
Time
08:15
08:30
09:15
09:30
09:45
10:00
10:15
10:30
10:45
12:15
12:30
12:45
13:00
13:15
13:30
13:45
15:50
16:00
16:15
16:30
16:45
17:00
Primary
Cooling Fan
(amps)
485
500
520
495
480
485
500
485
485
460
460
480
465
470
470
470
470
480
480
475
480
475
ID Fan (amps)
#1-1
497
490
493
485
490
491
484
487
495
485
483
485
480
485
483
477
504
491
499
496
503
499
#1-2
491
480
485
487
488
483
488
482
479
479
483
483
482
480
483
472
494
491
493
494
491
489
Average
480
490
485
2-10
-------
drop of the scrubber 1-1 was greater than the 10.5 in. W.C. desired during
this period.
2.3.4 Pressure Drop (Ap) Across Each Venturi Scrubber
Two scrubber pressure drop conditions were tested. These were 10.5
and 6.5 in. W.C. Condition A was 10.5 in. W.C. and condition B was
6.5 in. W.C. The pressure drop across each venturi was monitored during the
emission test period and recorded in Notebook #20880. Due to the
consistency of the recorded values, the pressure drop is not reproduced for
this document.
The only anomaly noted during the test period was the incorrect venturi
setting noted above. The incorrect setting was discovered during the
pressure sensor calibration on August 25th, prior to testing.
2.3.5 Scrubber Liquid Flow Rate for Each Scrubber
The liquid flow rate for each scrubber was monitored during each test
period. The liquid flow rates are summarized in Table 2-4. The total
liquid flow rate in gallons per minute (gpm) for each scrubber is the sum of
the two recorded values. The plant data acquisition system monitors the
water to both the main scrubber body and the demister (separator) section.
JES/045 2-11
-------
TABLE 2-4. VENTURI SCRUBBER WATER FLOW SUMMARY FOR FMC-POCATELLO, IDAHO (August 1988)
(Catciner #1)
Water Flow (qpm)
Date
8/23/88
8/23/88
8/23/88
8/23/88
8/23/88
8/23/88
8/23/88
8/23/88
8/23/88
8/23/88
Average
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
8/24/88
Average
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
8/25/88
Average
Time
10:36
11:00
11:15
12:00
12:30
12:45
13:00
13:15
15:15
16:00
09:30
09:45
10:00
11:08
11:50
12:38
13:11
13:50
14:16
14:44
16:15
16:45
17:20
17:40
18:00
18:18
18:30
11:24
11:45
12:00
12:30
14:30
16:00
17:20
17:46
18:20
18:35
18:50
19:05
19:20
19:35
19:50
20:05
20:20
20:35
20:50
#1
1524
1490
1490
1563
1495
1454
1449
1501
1403
1494
1486
1516
1523
1533
1549
1562
1527
1556
1556
1576
1551
1533
1551
1517
1501
1493
1484
1486
1530
1493
1444
1487
1456
1460
1491
1471
1512
1531
1411
1513
1538
1516
1539
1534
1499
1491
1543
1519
1497
Seperator
183
180
182
179
180
181
188
183
184
194
183
182
197
180
180
193
184
183
195
184
181
194
181
195
186
182
196
193
187
195
193
182
182
207
193
181
184
190
181
185
182
193
179
179
183
178
196
193
187
#2
1684
1692
1721
1716
1779
1715
1684
1764
1663
1758
1718
1743
1761
1779
1749
1800
1791
1763
1794
1723
1741
1818
1839
1818
1774
1769
1746
1783
1776
1818
1822
1781
1833
1776
1771
1557
1771
1723
1623
1756
1731
1767
1733
1733
1751
1726
1731
1776
1746
SeperltJ
185
191
185
189
192
192
201
192
191
196
191
190
189
191
190
194
186
185
193
187
187
188
188
201
188
189
188
193
190
19S
1 7J
189
197
186
192
186
184
191
184
193
184
191
185
192
182
192
184
194
189
2-12
-------
TABLE 2-4. (Continued)
(Calciner #1)
Date
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
8/26/88
Time
08:15
08:30
09:15
09:30
09:45
10:00
10:15
10:30
10:45
12:15
12:30
12:45
13:00
13:15
13:30
13:45
15:50
16:00
16:15
16:30
16:45
17:00
#1
1473
1437
1485
1466
1455
1546
1458
1416
1439
1473
1443
1455
1499
1522
1500
1454
1509
1500
1532
1485
1431
1478
Water Fl
Seperator
181
182
192
181
198
180
192
180
179
188
191
191
180
198
177
192
176
180
192
183
196
179
ow (gpm)
#2
1748
1684
1737
1722
1788
1760
1690
1730
1773
1749
1711
1733
1786
1774
1761
1690
1795
1837
1826
1799
1717
1792
Seperator
206
186
194
186
194
186
198
189
199
197
191
199
188
197
188
197
188
187
195
188
197
188
Average
1475
186
1755
193
2-13
-------
3.0 SUMMARY AND DISCUSSION OF RESULTS
The results of the August 1988 test program conducted at the FMC
facility are presented in this section. Radionuclide data that are
presented are not blank corrected. Field blanks were collected on both
inlet and outlet MM 111 trains and the results are presented and discussed
in Section 5.0 of this document. For reference purposes, the radionuclide
activities in the field blank collected at the inlet location were less than
2 percent of the average activities of the samples collected at that
location (1.5% for Po-210, 0.2% for Pb-210). At the outlet, the field blank
activities for Po-210 and Pb-210 were approximately 1.2 percent and
2.2 percent, respectively, of the average outlet sample activities.
Dual units (metric and English) are presented in each table where
applicable. The supporting data for the results are included in the
appendices (Volume II) of this report.
3.1 RESULTS FOR TEST CONDITION A: VENTURI PRESSURE DROP = 10.5 in. W.C.
3.1.1 Particulate Matter and Radionuclide Results
Particulate matter and associated radionuclide emissions were collected
simultaneously at each of the inlet/outlet offgas sampling locations using
a modification of EPA Method 111. An overview of results from the four
inlet/outlet test runs at test condition A is presented in Table 3-1.
Specific sampling measurements from each individual test run at condition A
are presented in Tables 3-2 through 3-5 for runs 1 through 4, respectively.
Slight deviations from the planned test matrix were made to compensate for
sampling difficulties encountered during testing. Two MM 111 sampling runs
were nonisokinetic at the inlet location. Also, the venturi scrubber
pressure drop was incorrectly set too high for scrubber 1-1 on 8/24/88. The
incorrect pressure drop was discovered during process instrumentation
calibration prior to testing on 8/25/88.
JES/045 3-1
-------
TABLE 3-1. SUMMARY OF PARTICULATE MATTER AND RADIONUCLIDE EMISSION RESULTS: CALCINER 1 OFFGASES, FMC-POCATELLO, IDAHO (August 1988)
Particulate
Run Concentration
Location Number (gr/dscf)
Inlet 1 0.3849
2 0.4983
3 0.4549
4 0.4962
Average 0.4755
(Runs 3-4)
Outlet 1 0.03918
(Scrubber
A? = 10.5 2 0.04584
in. W.C.)
3 0.04120
co
i
•^ 4 0.03944
Average 0.04142
(Runs 3-4)
Outlet*3 5 0.03362
(Scrubber
A? - 6.5 6 0.03776
in. W.C.)
7 0.03548
Average 0.03562
(Runs 5-7)
(mg/dscm)
880.8
1140
1041
1135
1088
89.64
104.9
94.28
90.24
94.76
76.93
86.40
81.18
81.50
Matter
Mass
(Ib/hr)
461.2
617.0
527.7
553.9
540.8
41.46
49.76
46.57
45.21
45.75
45.88
50.68
48.46
48.34
Polonium-210
Rate
(kg/hr)
209.2
279.9
240.6
251.3
245.9
18.81
22.57
21.12
20.51
20.75
20.81
22.99
21.98
21.93
Concentration
(pCi/dscf)
166.5
173.9
143.7
125.7
134.7
166.5
168.8
123.6
95.63
138.6
108.7
144.2
128.7
127.2
(pCi/dscm)
5880
6140
5074
4433
4755
5880
5958
4365
3377
4895
3840
5093
4544
4492
Emission
Rate
(uCi/hr)
1397
1507
1167
982.0
1075
1234
1283
978.0
767.4
1065
1039
1355
1230
1208
Activity: PM
(nCi/g PM)
6.676
5.385
4.875
3.907
4.391
64.75
55.78
46.95
37.40
51.22
49.83
60.11
55.92
55.29
Lead- 210
Concentration
(pCi/dscf)
3.361
2.274
2.834
8.217
5.526
1.233
2.486
8.596
1.027
3.336
0.8112
7.965E-05°
0.4656°
0.4256
(pCi/dscm)
118.7
80.27
100.1
290.0
195.0
43.53
87.78
303.5
36.27
118.8
28.64
2.813E-03°
16.44°
15.03
Emission
Rate
(uCi/hr)
28.19
19.71
23.01
64.22
43.62
9.134
18.90
68.00
8.244
26.07
7.749
7.483E-04°
4.451°
4.067
Activity: PM
(nCi/g PM)
0.1347
0.0704
0.0961
0.2555
0.1758
0.4706
0.8655
3.429
0.4012
1.291
0.3947
2.978E-05°
0.2036°
0.1995
Average inlet values from runs 3 and 4, the two valid inlet runs.
b
Outlet concentration values for each run are the averages of the two
are the sum of the mass rates for the two outlet locations.
outlet locations weighted for the different stack gas flow rates. The mass rates
Lead-210 was not detected in either the Outlet A or Outlet B samples. The values presented are an average minimum detection limit.
-------
TABLE 3-2.
SUMMARY OF MM 111 RESULTS FOR RUN 1, VENTURI PRESSURE DROP
CALCINER 1 OFFGASES, FMC-POCATELLO, IDAHO (August 1988)
10.5 in. W.C.,
Run 1 (8/24/88)
Sampling Parameters
Volume gas sampled (dscf)
Volume gas sampled (dscm)
Stack gas flow rate (dscfm)
Stack gas flow rate (dscmm)
Stack gas flow rate (acfm)
Stack gas flow rate (acrrm)
Stack temperature ( F)
Stack temperature ( C)
Moisture (percent by volume)
Isokinetics (percent)
Partieulate Emission Results
Particulate concentration (mg/dscm)
Particulate rate (kg/hr)
Radionuclide Emission Results
Polonium-210
(pCi/dscf )
(pCi/dscm)
(uCi/hr)
(nCi/g particulate)
Lead-210
(pCi/dscf)
(pCi/dscm)
(uCi/hr)
(nCi/g particulate)
Inlet
34.71
0.983
139,788
3,959
323,010
9,148
465.9
241.1
10.64
119.2
0 3849
880.8
461 . 2
209.2
166.5
5,880
1,397
6.676
3-361c'd
118'7c'd
28.19 ' .
c d
0.1347 '
Outlet A
35.06
0.993
55,401
1,569
87,874
2,489
131.5
55.3
17.36
97.9
0 03961
90.63
18 . 81
8.532
142.8
5,044
474.8
55.65
0.7932C'e
28.01°'e
C c
2.637 '
0.3090°'e
Outlet B
40.78
1.155
68,067
1,928
111,444
3,156
140.5
60.3
18.72
92.7
0 03883
88.84
22.65
10.28
185.8
6,560
758.8
73.84
1.591°'f
56.17°'^
c . f
6.497 '^
C I
0.6323 '
Average
Outlets A & B
—
--
123,468
3,497
199,318
5,645
136.0
57.8
18.04
"
0 . 03918
89.64
41 .46
18.81
166.5
5,880
1,234
64.75
1.233
43.53
9.134
0.4706
Pressure drop across the venturi was 13 in. W.C. for the "A" side. For the "B" side, the pressure
drop was 10.5 in. W.C., which was the target level.
Average concentrations weighted for stack gas flow for each stack. Stack gas flows and pollutant
mass flows are the total from both stacks.
CLead-210 was not detected in either the front half or back half fraction.
The inlet-Run 1 sample contained Pb-210 in the back half fraction at less than 0.0677 pCi/dscf.
6The outlet A-Run 1 sample contained Pb-210 in the front half fraction at less than 0.200 pCi/dscf.
The Outlet B-Run 1 sample contained Pb-210 in the front half fraction at less than 1.52 pCi/dscf.
3-3
-------
TABLE 3-3. SUMMARY OF MM 111 RESULTS FOR RUN 2, VENTURI PRESSURE DROP = 10.5 in.
CALCINER 1 OFFGASES, FMC-POCATELLO, IDAHO (August 1988)
W.C.,
Run 2 (8/24/88)
Inlet
Outlet A
Outlet B
Average
Outlets A & B
Sampling Parameters
Volume gas sampled (dscf) 35.73 34.81 42.12
Volume gas sampled (dscm) 1.012 0.986 1.193
Stack gas flow rate (dscfm) 144,456 57,019 69,639 126,658
Stack gas flow rate (dscmm) 4,091 1,615 1,972 3,587
Stack gas flow rate (acfm) 327,672 90,039 111,292 201,331
Stack gas flow rate (acnrn) 9,280 2,550 3,152 5,702
Stack temperature (°F) 466.3 133.1 136.2 134.6
Stack temperature (°C) 241.3 56.16 57.87 57.01
Moisture (percent by volume) 8.65 16.74 17.33 17.04
Isoklnetlcs (percent) 118.8 94.5 93.6
Partlculate Emission Results
Partlculate concentration (gr/dscf) 0.4983 0.04491 0.04660 0.04584
Particulate concentration (mg/dscm) 1,140 102.8 106.6 104.9
Particulate rate (Ib/hr) 617.0 21.95 27.82 49.76
Particulate rate (kg/hr) 279.9 9.956 12.62 22.57
Radionuclide Emission Results
Polonium-210
(pCi/dscf)
(pCi/dscm)
(uCi/hr)
(nCi/g particulate)
Lead-210
(pCi/dscf)
(pCi/dscm)
(uCi/hr)
(nCi/g particulate)
173.9
6,
1,
5.
2.
80
19
0.
140
507
385
274
.27
.71
07039
137.0
4,838
468.8
47.08
3.225°'
113.8°'
11.03°'
1.108°'
d
d
d
d
194.7
6,876
813.7
64.48
1.882°'c
66.44°'"
7.863°'e
0.6231°'c
168.8
5,
1,
55
2.
87
18
0.
958
283
.78
486
.78
.90
8655
Pressure drop across the venturi was 13 in. W.C. for the "A" side. For the "B" side, the pressure
drop was 10.5 In. W.C., which was the target level.
b
Average concentrations weighted for stack gas flow rates. Stack gas flows and pollutant mass flows
are the total from both stacks.
Lead-210 was not detected in the back half fraction.
i
The Outlet A-Run 2 sample contained Pb-210 in the back half fraction at less than 0.040 pCi/dscf.
The Outlet B-Run 2 sample contained Pb-210 in the back half fraction at less than 0.019 pCi/dscf.
3-4
-------
TABLE 3-4. SUMMARY OF MM 111 RESULTS FOR RUN 3, VENTURI PRESSURE DROP
CALCINER 1 OFFGASES, FMC-POCATELLO, IDAHO (August 1988)
10.5 In. W.C.,
Run 3 (8/25/88)
Inlet
Outlet A
Outlet B
Average
Outlets A 4 B
Sampling Parameters
Volume gas sampled (dsof) 29.37 40.51 41.59
Volume gas sampled (dscm) 0.832 1.147 1.178
Stack gas flow rate (dscfm) 135,330 66,524 65,328 131,852
Stack gas flow rate (dscmm) 3,853 1,884 1,850 3,734
Stack gas flow rate (acfm) 321,407 109,624 109,183 218,807
Stack gas flow rate (acmm) 9,102 3,105 3,092 6,197
Stack temperature (°F) 474.9 136.7 140.5 138.6
Stack temperature (°C) 246.0 58.15 60.28 59.21
Moisture (percent by volume) 11.63 19.60 20.13 19.87
Isokinetlcs (percent) 104.2 94.2 99.3
Particulate Emission Results
Partlculate concentration (gr/dscf) 0.4549 0.04388 0.03848 0.04120
Particulate concentration (mg/dscm) 1041 100.4 88.04 94.28
Particulate rate (Ib/hr) 527.7 25.02 21.55 46.57
Particulate rate (kg/hr) 240.6 11.35 9.773 21.12
Radionuclide Emission Results
Polonium-210
(pCi/dscf)
(pCi/dscm)
(uCi/hr)
(nCi/g particulate)
Lead-210
(pCi/dscf)
(pCi/dscm)
(uCi/hr)
(nCi/g particulate)
143.7
5,074
1,167
4.875
b c
2.834^'°
ioo.i^'c
D C
23.01 'Ł
0.09612 'c
108.8
3,843
434.3
38.27
1.769
62.49
7.062
0.6223
138.7
4,898
543.8
55.63
b
15.55 '
548.9 '
60.94:"'
D .
6.235
d.
d
d
d
123.6
4,365
978.0
46.95
8.596
303.5
68.00
3.429
aAverage concentrations weighted for stack gas flow rates. Stack gas flows and pollutant mass
flows are the total from both stacks.
Lead-210 was not detected in the back half fraction.
CThe inlet-Run 3 sample contained Pb-210 in the back half fraction at less than 0.033 pCi/dscf.
The Outlet B-Run 3 sample contained Pb-210 in the back half fraction at less than 0.013 pCI/dscf.
3-5
-------
TABLE 3-5. SUMMARY OF MM 111 RESULTS FOR RUN It, VENTURI PRESSURE DROP = 10.5 in. W.C.,
CALCINER 1 OFFGASES, FMC-POCATELLO, IDAHO (August 1988)
Run A (8/25/88)
Sampling Parameters
Volume gas sampled (dscf)
Volume gas sampled (dscm)
Stack gas flow rate (dscfm)
Stack gas flow rate (dscmm)
Stack gas flow rate (acfm)
Stack gas flow rate (acmm)
o
Stack temperature ( F)
Stack temperature ( C)
Moisture (percent by volume)
Isokinetics (percent)
Particulate Emission Results
Particulate concentration (gr/dscf)
Particulate rate (kg/hr)
Radionuclide Emission Results
Polonium-210
(pCi/dscf)
(pCi/dscm)
(uCi/hr)
(nCi/g particulate)
Lead- 210
(pCi/dscf)
(pCi/dscm)
(uCi/hr)
(nCi/g particulate)
Inlet
26.93
0.763
130,246
3,689
296,961
8,410
446.0
230.0
10.45
99.3
0.4962
1135
553 . 9
251.3
125.7
4,435
982.0
3.907
8.217
290.0
64.22
0 . 2555
Outlet A
40.50
1.147
66,661
1,888
107,682
3,050
133.5
56.39
17.94
94.0
0.04012
91 80
22. 92
10.40
99.62
3,517
398.4
38.32
ND [1.183]:'
ND [41.77]:'
ND [4.732]
ND [0.4550]
Outlet B
42.12
1.193
67,085
1,900
109,488
3,101
138.0
58.89
18.16
97.9
0.03876
88 . 69
22. 29
10.11
91.67
3,237
369.0
36.49
0.8727
30.81
3.513
0.3474
a
Average
Outlets A & B
—
—
133,746
3,788
217,170
6,151
135.8
57.64
18.05
""
0.03944
90 . 24
45 .21
20.51
95.63
3,377
767.4
37.40
1.027
36.27
8.244
0.4012
Average concentrations weighted for stack gas flow rates. Stack gas flows and pollutant mass are the
total from both stacks.
b
Lead-210 was not detected in the Outlet A-Run 4 sample. The value in brackets is the minimum
detection limit.
3-6
-------
To compensate for these difficulties, a fourth MM 111 test run was performed
at each of the inlet and outlet locations.
Data from all test runs are presented in the summary tables of this
report, although only those runs meeting the specified quality assurance
criteria were used in the reported average results.
3.1.1.1 Inlet. Particulate matter concentrations at the inlet to the
venturi scrubber averaged 1,088 mg/dscm (0.476 gr/dscf) for the two valid
test runs. These values represent uncontrolled emissions from the calciner.
Po-210 concentrations in flue gases at the inlet location averaged
4,755 pCi/dscm (135 pCi/dscf) for the two valid test runs. On an activity
per gram of particulate basis, values for the two inlet runs averaged
4.39 nCi/g PM.
Pb-210 concentrations in flue gases at the inlet location averaged
195 pCi/dscm (5.53 pCi/dscf). On an activity per gram of particulate basis,
values for the two inlet runs averaged 0.176 nCi/g PM.
3.1.1.2 Outlet. As shown in Table 3-1, particulate matter
concentration at the outlet during Test Condition A averaged 94.8 mg/dscm
(0.0414 gr/dscf). For all of the runs, particulate matter emissions were
evenly distributed between the outlet's two locations. Even during MM 111
runs 1 and 2, where the pressure drop across scrubber 1-1 was approximately
3 inches greater than that for scrubber 1-2, the distribution was fairly
even.
Po-210 concentrations in flue gases at the outlet location averaged
4,895 pCi/dscm (139 pCi/dscf) for the four test runs. On an activity per
gram of particulate basis, Po-210 activity for the outlet runs averaged
51.2 nCi/g PM. The Po-210 concentration was also evenly distributed between
the outlet's two locations.
Pb-210 concentrations in flue gases at the outlet location averaged
119 pCi/dscm (3.34 pCi/dscf). On an activity per gram of particulate basis,
Pb-210 activity averaged 1.29 nCi/g PM. The Pb-210 concentrations were at
or near the minimum detection limit where the analytical precision is
less. Thus, although the concentrations at the two outlet locations appear
to differ, they are actually agreeing within analytical precision.
JES/045 3-7
-------
3.1.1.3 Venturi Scrubber Efficiencies - Method 111. Table 3-6
summarizes the removal efficiencies of the venturi scrubber control systems
for removal of particulate, Po-210, and Pb-210. Although removal
efficiencies are reported for all four runs, the average values are based on
the results from runs 3 and 4. The removal efficiencies for each run were
calculated from the inlet and total outlet emission rates. Removal
efficiency for PM was consistent for all the runs, averaging above
91 percent. The scrubber removed an average of 19 percent of the inlet
Po-210, with the removal relatively consistent for the different runs.
The Pb-210 concentrations were at or near the minimum detection limit
for both the inlet and outlet. Although the calculated Pb-210 removal
efficiencies ranged from -195 to 87.2 percent, the actual removal efficiency
was near zero.
3.1.1.4 Front/Back Half Distribution of Emissions in MM 111 Trains.
Table 3-7 presents a summary of the distribution of emissions as collected
in the MM 111 sampling trains during test condition A. As seen in the
table, 97 to 99 percent of the Po-210 collected was present in the front
half of the train. This percentage was consistent for samples collected at
both inlet and outlet locations. The distribution for Pb-210 was similar;
about 95 to 98 percent was collected in the front half. A distribution of
Po-210 and Pb-210 between front half sampling train components was beyond
the scope of this test project, due to analysis volume and regulatory
schedule.
The distribution of PM between the front half components was evaluated.
As seen in the footnotes to Table 3-7, the average distribution of PM among
the front half components varied by the sampling location as expected. On
average, 16 percent of the PM collected at the inlet was found on the
filter, while the remaining 84 percent was collected in the probe and
nozzle. At the outlet, the average distribution was approximately
86 percent on the filter and 14 percent in the probe and nozzle.
JES/045 3-8
-------
TABLE 3-6. VENTURI SCRUBBER REMOVAL EFFICIENCY FOR PM, Po, AND Pb:
PRESSURE DROP = 10.5 in. W.C., CALCINER 1 OFFGASES,
FMC-POCATELLO, IDAHO (August 1988)
Concentration
Inlet
Outlet
Removal
Efficiency
(percent)
Run 1
Particulate (gr/dscf)
Po-210 (pCi/dscf)
Pb-210 (pCi/dscf)
Run 2
Particulate (gr/dscf)
Po-210 (pCi/dscf)
Pb-210 (pCi/dscf)
Run 3
Particulate (gr/dscf)
Po-210 (pCi/dscf)
Pb-210 (pCi/dscf)
Run 4
Particulate (gr/dscf)
Po-210 (pCi/dscf)
Pb-210 (pCi/dscf)
0.3849
166.5
3.361
0.4983
173.9
2.274
0.4549
143.7
2.834
0.4962
125.7
8.217
0.03918
166.5
1.233
0.04584
168.8
2.486
0.04120
123.6
8.596
0.0394
95.63
1.028
91.01
11.67
67.60
91.93
14.91
4.112
91.18
16.21,
-195.5C
91.84
21.85
87.16
Average
Particulate (gr/dscf)
Po-210 (pCi/dscf)
Pb-210 (pCi/dscf)
r-
0.4755^
134.7^
5.526C
0.04142
138.6
3.336
91.51-
19.03:;
43.58
Removal efficiencies calculated based on mass flow rates of PM, Po, and Pb.
DIf the removal efficiency is less than zero, the inlet and outlet values
should be considered equal taking into account the precision of the
sampling and analytical methods. The removal efficiency should be
considered zero.
"Average of runs 3 and 4.
JES/045
3-9
-------
TABLE 3-7. SUMMARY OF FRONT/BACK HALF DISTRIBUTION OF EMISSIONS:
MM 111 SAMPLING TRAINS, PRESSURE DROP = 10.5 in. W.C.,
CALCINER 1 OFFGASES, FMC-POCATELLO, IDAHO (August 1988)
Location
Inlet
Outlet
Parameter
Particulate
Po-210
Pb-210
Particulate
Po-210
Pb-210
Front Half
100a
96.6
98.2
100°
99.2
95.1
Back Half
NAb
3.4
1.8
NA
0.8
4.9
On average, 16 percent of the particulate matter collected at the inlet was
found on the filter, while the remaining 84 percent was collected in the
probe and nozzle.
NA = Not applicable. The addition of 0.1 N HNO., in the impingers prevented
drying and weighing of the impinger catch.
C0n average, 86 percent of the particulate matter collected at the outlet was
found on the filter, and 14 percent was collected in the probe and nozzle.
JES/045 3-10
-------
3.1.2 Particle and Radionuclide Size Distribution Data
The PSD samples were analyzed for both particulate mass and Po-210/
Pb-210 radioactivity. For the particulate mass analyses, each of the nine
individual stages were analyzed separately. For the radionuclide analyses,
stages 2-5 were combined and stages 1, 6, 7, 8, and 9 were analyzed
individually. The particulate and radionuclide results are discussed below.
3.1.2.1 Particle Size Distribution Data. The mass collected on each
stage was presented previously in Table 1-4 in Section 1.0. These data were
presented two ways: first as a plot of cumulative mass fraction versus the
particle interval endpoint (Dp50) and second as a plot of differential mass
concentration versus the geometric mean particle diameter. The individual
data points were plotted and curves were fitted to the data to represent the
characteristics of the particulate matter at each sampling location. From
the composite curves, cumulative mass fractions could be determined for the
particle sizes of interest: 0.5, 1, 2.5, 5, and 10 microns. The composite
curves were presented previously in Figures 1-1 and 1-2.
For the cumulative mass fraction results, the individual inlet data
are shown in Figure 3-1 and outlet data are shown in Figure 3-2. The inlet
test runs agreed well and formed a linear curve. The outlet data show that
particle characteristics were similar at the two outlet locations and also
formed a linear curve. The data are presented in tabular form in Tables 3-8
and 3-9.
For the differential mass concentrations, the individual inlet data
are plotted in Figure 3-3 and the outlet data pairs are plotted in
Figure 3-4. The data are presented in tabular form in Tables 3-10 and 3-11.
3.1.2.2 Radionuclide Distribution Data. The radioactivity collected
on each stage was presented previously in Table 1-8. In order to evaluate
the radionuclide data, the cumulative activity fraction was plotted against
the interval endpoint (Dp5Q) determined from the PSD data.
JES/045 3-11
-------
c
CD
H
to
01
g
'•*-»
o
(D
03
VI
CD
0)
'
_
3
E
3
CJ
Figure 3-1. Cumulative mass fraction as a function of particle size for
particulate matter at the venturi scrubber inlet.
Probability-Log plot, Calciner 1 offgases.
FMC, Pocatello, Idaho (August 1988).
JES/045
3-12
-------
03
CO
CO
c
o
CD
CO
CO
CO
0>
'
3
E
3
u
Dpso (microns)
Figure 3-2. Cumulative mass fraction as a function of particle size for
particulate matter at the venturi scrubber outlet.
Probability-Log plot, Calciner 1 offgases.
FMC, Pocatello, Idaho (August 1988).
JES/045
3-13
-------
TABLE 3-8. CUMULATIVE MASS FRACTION VS. PARTICLE SIZE FOR SCRUBBER INLET PARTICULATE,
VENTURI PRESSURE DROP = 10.5 in. W.C., CALCINER 1, FMC-POCATELLO, IDAHO
(August 1988)
CO
I
Stage
1
2
3
4
5
6
7
8
Inlet - Run 1 Inlet - Run 2 Inlet - Run 3
b b b
Mass Fraction Mass Fraction Mass Fraction
Dp * Less Than ^so* Less Than Dp Less Than
11.70 0.2304 11.69 0.1417 11.96 0.0897
7.639 0.2111 7.637 0.1144 7.814 0.0638
4.984 0.1872 4.983 0.0895 5.099 0.0408
3.520 0.0762 3.519 0.0713 3.600 0.0338
2.084 0.0695 2.084 0.0575 2.131 0.0292
1.183 0.0386 1.184 0.0474 1.209 0.0232
0.7246 0.0352 0.7267 0.0445 0.7385 0.0232
0.4576 0.0256 0.4611 0.0395 0.4636 0.0232
Dp = The theoretical stage endpoint (interval endpoint) is the aerodynamic diameter of the smallest particles
collected on a stage with an efficiency of 50 percent.
The cumulative mass fraction equals the mass fraction of particulate collected less than a given Interval endpoint.
-------
TABLE 3-9. CUMULATIVE MASS FRACTION VS. PARTICLE SIZE FOR SCRUBBER OUTLET PARTICULATE, VENTURI PRESSURE DROP = 10.5 in. W.C.,
CALCINER 1, FMC-POCATELLO, IDAHO (August 1988)
CO
I
en
Outlet A - Run 1 Outlet A - Run 2
Mass Fraction Mass Fraction
Stage DP5n Less Than ®P$n Less Than
1 11.10 0.9927 12.07 0.9817
2 7.251 0.9883 7.881 0.9715
3 4.731 0.9746 5.141 0.9575
4 3.340 0.9728 3.630 0.9387
5 1.977 0.9496 2.148 0.9191
6 1.121 0.9176 1.217 0.8906
7 0.6840 0.8765 0.7414 0.8514
8 0.4282 0.7864 0.4622 0.7898
Outlet A - Run 3 Outlet B - Run 1
b b
Mass Fraction Mass Fraction
Dp Less Than DP50 Less Than
10.84 0.9912 11.29 0.9773
7.079 0.9836 7.373 0.9611
4.619 0.9734 4.811 0.9425
3.261 0.9637 3.398 0.9239
1.930 0.9441 2.012 0.8993
1.094 0.9177 1.143 0.8769
0.6676 0.8683 0.7010 0.8401
0.4178 0.6913 0.4441 0.7804
Outlet B - Run 2 Outlet B - Run 3
Mass Fraction Mass Fraction
Dp Less Than Dp,n Less Than
10.94 0.9865 10.60 0.9912
7.144 0.9771 6.923 0.9876
4.662 0.9647 4.517 0.9807
3.292 0.9528 3.190 0.9686
1.949 0.9307 1.889 0.9513
1.107 0.9008 1.074 0.9253
0.6792 0.8668 0.6597 0.8563
0.4304 0.7862 0.4194 0.6822
Dp = The theoretical stage endpoint (interval endpoint) is the aerodynamic diameter of the smallest particles collected on a stage with
an efficiency of 50 percent.
The cumulative mass fraction equals the mass fraction of particulate collected less than a given interval endpoint.
-------
0 10
e/)
T5
Q 10
CD
O
-O 10 -3-
10
a
0
Inlet
a a a a a Run 1
A A A A A Run 2
ooooo Run 3
0.01
0.1
Aerodynamic
1 10
Particle Diameter (um)
Figure 3-3. Differential mass concentration as a function of particle size
for venturi scrubber inlet particulate matter.
Probability-Log plot, Calciner 1 offgases.
FMC, Pocatello, Idaho (August 1988)
3-16
-------
(_> 10
(/I
"U
CL
Q 10 "'
O
_l
t>
\
2
"D 10 '
10 "
0.01
Outlet A
o o o a a Run 1
4 o a a a Run 2
ooooo Run 3
O.I 1 10
Aerodynamic Particle Diameter (urn)
-------
TABLE 3-10. DIFFERENTIAL MASS CONCENTRATION VS. PARTICLE SIZE FOR SCRUBBER INLET PARTICULATE,
VENTURI PRESSURE DROP = 10.5 In. W.C., CALCINER 1, FMC-POCATELLO, IDAHO (August 1988)
CO
I
00
Stage
1
2
3
4
5
6
7
8
Back-up
Inlet - Run 1 Inlet - Run 2
Geometric' Differential Geometric3 Differential
Midpoint Mass Midpoint Mass
24.18 0.5613 24.18 0.5957
9.452 0.0480 9.449 0.0646
6.170 0.0593 6.169 0.0588
4.188 0.3380 4.188 0.0530
2.708 0.0137 2.708 0.0265
1.570 0.0578 1.571 0.0180
0.9259 0.0073 0.9277 0.0060
0.5758 0.0222 0.5789 0.0112
0.0478 0.0060 0.0480 0.0088
Inlet - Run 3
Geometric Differential
Midpoint Mass
24.46 0.7960
9.669 0.0758
6.312 0.0674
4.284 0.0252
2.770 0.0110
1.605 0.0132
0.9447 0.0000
0.5851 0.0000
0.0481 0.0064
Geometric midpoint is defined as:
,1/2
Differential mass concentration (gr/dscf) is defined as:
mass on stage "n" /\ M
50 n+1 40 n ^"^
-------
TABLE 3-11. DIFFERENTIAL MASS CONCENTRATION VS. PARTICLE SIZE FOR SCRUBBER OUTLET PARTICIPATE,
VENTURI PRESSURE DROP = 10.5 In. W.C., CALCINER 1, FMC-POCATELLO, IDAHO (August 1988)
CO
I
OAitlet A
- Run 1
Outlet A
Geometric Differential Geometric
Stage Midpoint Mass Midpoint
1 23.56
2 8.973
3 5.857
4 3.975
5 2.570
6 1.488
7 0.8755
8 0.5412
Back-up 0.0463
0.0004
0.0008
0.0026
0.0004
0.0035
0.0045
0.0066
0.0153
0.0141
24.56
9.751
6.365
4.320
2.792
1.617
0.9498
0.5854
0.0481
- Run 2
Outlet A
b a
Differential Geometric
Mass Midpoint
0.0008
0.0016
0.0021
0.0035
0.0024
0.0033
0.0051
0.0085
0.0113
23.28
8.760
5.718
3.881
2.509
1.453
0.8546
0.5281
0.0457
- Run 3
Outlet B
- Run 1
Outlet B - Run 2
Differential Geometric Differential Geometric
Mass Midpoint Mass Midpoint
0.0004
0.0013
0.0017
0.0020
0.0026
0.0032
0.0070
0.0263
0.0109
23.76
9.124
5.956
4.043
2.614
1.516
0.8951
0.5580
0.0471
0.0012
0.0031
0.0036
0.0044
0.0038
0.0032
0.0062
0.0107
0.0142
23.39
8.840
5.771
3.917
2.533
1.469
0.8673
0.5407
0.0464
Outlet B - Run 3
Differential Geometric Differential
Mass Midpoint Mass
0.0007
0.0017
0.0022
0.0026
0.0032
0.0040
0.0052
0.0133
0.0133
23.02
8.566
5.592
3.796
2.455
1.424
0.8417
0.5260
0.0458
0.0004
0.0006
0.0012
0.0026
0.0024
0.0034
0.0104
0.0283
0.0113
Geometric midpoint is defined as:
,1/2
Differential mass concentration (gr/dscf) is defined as:
mass on stage "n" i\ M
P40 n
-------
The polonium-210 and lead-210 data were plotted separately. The inlet
and outlet polonium-210 cumulative activities are plotted in Figures 3-5
and 3-6, respectively. The data showed good agreement between runs and
formed a linear curve.
The inlet and outlet lead-210 cumulative activities are plotted in
Figures 3-7 and 3-8, respectively. The inlet and outlet data are presented
in tabular form in Tables 3-12 and 3-13. The Pb-210 data contained
considerably more variability than the Po-210 data, although the data still
formed linear curves. The variability is believed to be due to the fact
that the Pb-210 concentrations were at or near the minimum detection limits.
3.1.3 Process Samples
Table 3-14 presents the measured concentrations of Po-210 and Pb-210 in
the feedstock samples. The average concentrations of these radionuclides in
the feedstock samples were 23.271 and 24.000 pCi/g, respectively. The
concentrations varied between runs by 2.9 percent for Po-210 and 13 percent
for Pb-210, indicating a constant level of radioactivity in the feedstock.
3.2 RESULTS FOR TEST CONDITION B: VENTURI PRESSURE DROP = 6.5 in. W.C.
Particulate matter and associated radionuclide emissions were measured
at the outlet stacks for three runs at test condition B. No Method 111
samples were collected at the inlet. No particle sizing samples were
collected during test condition B, either. The results from condition B are
summarized in Table 3-1. The specific sampling results for each of the test
runs are presented in Tables 3-15 through 3-17.
3.2.1 Outlet Particulate Matter and Radionuclide Results
As shown in Table 3-1, particulate matter concentration at the outlet
averaged 81.5 mg/dscm (0.0356 gr/dscf). For all of the runs, particulate
matter and Po-210 emissions were evenly distributed between the outlet's two
locations.
JES/045 3-20
-------
c
ta
-------
100
Figure 3-6. Cumulative Polonium-210 activity fraction as a function of
particle size for particulate matter at the venturi scrubber outlet.
Probability-Log plot, Calciner 1 offgases.
FMC, Pocatello, Idaho (August 1988).
JES/045
3-22
-------
DpM (microns)
Figure 3-7. Cumulative Lead-210 activity fraction as a function of
particle size for particulate matter at the venturi scrubber inlet.
Probability-Log plot, Calciner 1 offgases.
FMC, Pocatello, Idaho (August 1988).
JES/045
3-23
-------
DpM (microns)
Figure 3-8. Cumulative Lead-210 activity fraction as a function of
particle size for particulate matter at the venturi scrubber outlet.
Probability-Log plot, Calciner 1 offgases.
FMC, Pocatello, Idaho (August 1988).
JES/045
3-24
-------
TABLE 3-12. CUMULATIVE ACTIVITY FRACTION FOR SCRUBBER INLET PARTICULATE, VENTURI PRESSURE DROP = 10.5 In. W.C.,
CALCINER 1, FMC-POCATELLO, IDAHO (August 1988)
Inlet - Run 1
Stage Dp Po-210 Pb-210
Inlet - Run 2
Dp * Po-210b Pb-210b
Inlet - Run 3
Dp
50
Po-210 Pb-210
11.70 0.9297 0.7443 11.69 0.9293 0.8822 11.96 0.8766 0.7146
2-5
2.084 0.8267 0.2275 2.084 0.8028 0.5890 2.131 0.6484 0.5866
1.183 0.7756 0.0000 1.184 0.7479 0.5307 1.209 0.6032 0.5025
0.7246 0.7219 0.0000 0.7267 0.6714 0.4308 0.7385 0.5648 0.3414
ro
en
0.4576 0.6616 0.0000 0.4611 0.5745 0.2689 0.4636 0.5181 0.2979
I)P =* The theoretical stage endpoint (Interval endpoint) is the aerodynamic diameter of the smallest particles
collected on a stage with an efficiency of 50 percent.
The cumulative activity fraction is the fraction of activity emitted by particles less than or equal to the given
interval endpoint (Dp ).
-------
TABLE 3-13. CUMULATIVE ACTIVITY FRACTION FOR SCRUBBER OUTLET PARTICULATE, VENTURI PRESSURE DROP = 10.5 In. W.C.
CALCINER 1, FMC-POCATELLO, IDAHO (August 1988)
Outlet A - Run 1 Outlet A - Run 2 Outlet A - Run 3 Outlet B - Run 1 Outlet B - Run 2 Outlet B - Run 3
Stage "PSQ* p°~2l°b Pt>-210b Dp^" Po-21Qb Pb-210b Dp * Po-21Qb Pb-210b Dp a Po-210b Pb-210b Dp5Q Po-210b Pb-210b Dp5Qa Po-210b Pb-21Qb
1 11.10 0.9646 0.9858 12.07 0.9644 0.9489 10.84 0.9922 0.9277 11.29 0.9802 1.0000 10.94 0.9815 1.0000 10.60 0.9806 1.0000
2-5 1.977 0.8688 0.9124 2.148 0.8431 0.7656 1.930 0.9515 0.8438 2.012 0.9178 0.8369 1.949 0.9202 0.9984 1.889 0.9200 1.0000
6 1.121 0.8385 0.4517 1.217 0.8101 0.7218 1.094 0.9329 0.7660 1.143 0.9039 0.8170 1.107 0.8981 0.9942 1.074 0.8973 0.9834
7 0.6840 0.7860 0.3674 0.7414 0.7648 0.6678 0.6676 0.8889 0.6797 0.7010 0.8752 0.6530 0.6792 0.8586 0.8018 0.6597 0.8295 0.9834
8 0.4282 0.6965 0.3674 0.4622 0.7196 0.5409 0.4178 0.7640 0.4977 0.4441 0.8119 0.2463 0.4304 0.7722 0.7284 0.4194 0.6460 0.0000
CO
I • • • •
f^> a
O1 DP = The theoretical stage endpoint (Interval endpolnt) is the aerodynamic diameter of the smallest particles collected on a stage with an
efficiency of 50 percent.
The cumulative activity fraction is the fraction of activity emitted by particles less than or equal to the given interval endpoint (Dp ) .
-------
TABLE 3-14. RADIONUCLIDE CONCENTRATIONS IN PROCESS FEEDSTOCK SAMPLES
CALCINER 1, FMC-POCATELLO, IDAHO (August 1988)
MM 111
Type of Sample Run No.
Feedstock 1
Feedstock 2
Feedstock 3
Feedstock 4
Average
Relative standard deviation (%)
Radionuclide Concentration
Date
8/24/88
8/24/88
8/25/88
8/25/88
Po-210
24.167
23.010
23.347
22.559
23.271
2.9
Pb-210
24.157
27.947
20.662
23.234
24.000
13
JES/045
3-27
-------
TABLE 3-15. SUMMARY OF MM 111 RESULTS FOR RUN 5, VENTURI PRESSURE DROP =
6.5 in. W.C., CALCINER 1 OFFGASES, FMC-POCATELLO, IDAHO
Run 5
(8/26/88)
Sampling Parameters
Volume gas sampled (dscf)
Volume gas sampled (dscm)
Stack gas flow rate (dscfm)
Stack gas flow rate (dscmm)
Stack gas flow rate (acfm)
Stack gas flow rate (acmm)
Stack temperature ( F)
Stack temperature ( C)
Moisture (percent by volume)
Isokinetics (percent)
Particulate Emission Results
Particulate concentration (gr/dscf)
Particulate concentration (mg/dscm)
Particulate rate (Ib/hr)
Particulate rate (kg/hr)
Radionuclide Emission Results
Polonium-210
(pCi/dscf)
(pCi/dscm)
(uCi/hr)
(nCi/g particulate)
Lead-210
(pCi/dscf)
(pCi/dscm)
(uCi/hr)
(nCi/g particulate)
Outlet
A
50.05
1.417
80,896
2,291
131,443
3,722
134.3
56.9
18.30
95.7
0.03499
80.07
24.26
11.01
116.0
4,097
563.0
51.17
0.01259°
0.4447°
0.06111°
0.005554°
Outlet
B
49.40
1.399
78,320
2,218
127,900
3,622
137.8
58.8
18.63
98.4
0.03220
73.69
21.62
9.807
101.2
3,574
475.6
48.50
1.636
57.77
7.688
0.7839
Average
Outlet
A & B
—
—
159,215
4,509
259,342
7,345
136.0
57.8
18.47
—
0.03362
76.93
45.88
20.81
108.7
3,840
1,039
49.83
0.8112
28.64
7.749
0.3947
Average concentrations weighted for stack gas flow for each stack. Stack
gas flows and pollutant mass flows are the total from both stacks.
Lead-210 was not detected in the back half fraction. The minimum detection
limit was less than zero.
JES/045
3-28
-------
TABLE 3-16.
SUMMARY OF MM 111 RESULTS FOR RUN 6, VENTURI PRESSURE DROP =
6.5 in. W.C., CALCINER 1 OFFGASES, FMC-POCATELLO, IDAHO
Run 6
(8/26/88)
Outlet
A
Outlet
B
Average3
Outlet
A & B
Sampling Parameters
Volume gas sampled (dscf)
Volume gas sampled (dscm)
Stack gas flow rate (dscfm)
Stack gas flow rate (dscmm)
Stack gas flow rate (acfm)
Stack gas flow rate (acmm)
Stack temperature ( F)
Stack temperature ( C)
Moisture (percent by volume)
Isokinetics (percent)
Particulate Emission Results
Particulate
Particulate
Particulate
Particulate
concentration
concentration
rate (Ib/hr)
rate (kg/hr)
(gr/dscf)
(mg/dscm)
49.58
1.404
78,000
2,209
129,184
3,658
136.3
57.92
19.59
98.4
0.04143
94.80
27.70
12.56
49.44
1.400
78,584
2,225
130,043
3,683
140.5
60.28
18.95
98.1
0.03412
78.06
22.98
10.42
Radionuclide Emission Results
Polonium-210
(pCi/dscf)
(pCi/dscm)
(uCi/hr)
(nCi/g particulate)
127.7
4,511
597.8
47.58
160.5
5,670
757.0
72.63
156,583
4,434
259,227
7,341
138.4
59.10
19.27
0.03776
86.40
50.68
22.99
144.2
5,093
1,355
60.11
Lead-210
(pCi/dscf)
(pCi/dscm)
(uCi/hr)
(nCi/g particulate)
ND [1.599E-04]? ND^
ND [5.646E-03]? ND^
ND [7.483E-04]P ND^
ND [5.956E-05]0 NDL
ND [7.965E-05]
ND [2.813E-03]
ND [7.483E-04]
ND [2.978E-05]
aAverage concentrations weighted for stack gas flow for each stack. Stack
gas flows and pollutant mass flows are the total from both stacks.
bLead-210 was not detected in the Outlet A-Run 6 sample. The values
presented are minimum detection limits.
cLead-210 was not detected in the Outlet B-Run 6 samples. The minimum
detection limit was below zero.
JES/045
3-29
-------
TABLE 3-17. SUMMARY OF MM 111 RESULTS FOR RUN 7, VENTURI PRESSURE DROP =
6.5 in. W.C., CALCINER 1 OFFGASES, FMC-POCATELLO, IDAHO
Run 7
(8/26/88)
Sampling Parameters
Volume gas sampled (dscf)
Volume gas sampled (dscm)
Stack gas flow rate (dscfm)
Stack gas flow rate (dscmm)
Stack gas flow rate (acfm)
Stack gas flow rate (acmm)
Stack temperature ( F)
Stack temperature ( C)
Moisture (percent by volume)
Isokinetics (percent)
Particulate Emission Results
Particulate concentration (gr/dscf)
Particulate concentration (mg/dscm)
Particulate rate (Ib/hr)
Particulate rate (kg/hr)
Radionuclide Emission Results
Polonium-210
(pCi/dscf)
(pCi/dscm)
(uCi/hr)
(nCi/g particulate)
Lead-210
(pCi/dscf)
(pCi/dscm)
(uCi/hr)
(nCi/g particulate)
Outlet
A
50.75
1.437
81,082
2,296
133,928
3,793
135.9
57.73
19.42
96.9
0.03467
79.32
24.10
10.93
105.1
3,713
511.5
46.82
i
0.8930°
31.54°
4.344°
0.3976°
Outlet
B
49.28
1.396
78,254
2,216
130,576
3,698
141.2
60.65
19.53
98.2
0.03632
83.11
24.36
11.05
153.1
5,404
718.8
65.02
ND [0.02282]C
ND [0.8055]C
ND [0.1071]cr
ND [0.009692]c
Average3
Outlet
A & B
—
—
159,336
4,512
264,504
7,491
138.5
59.19
19.48
—
0.03548
81.18
48.46
21.98
128.7
4,544
1,230
55.92
0.4656
16.44
4.451
0.2036
Average concentrations weighted for stack gas flow for each stack. Stack
gas flows and pollutant mass flows are the total from both stacks.
DLead-210 was not detected in the back half fraction of the Outlet A-Run 7
sample. The minimum detection limit was below zero.
'Lead-210 was not detected in either the front half or back half fraction of
the Outlet B-Run 7 sample. The values presented are minimum detection
limits.
JES/045
3-30
-------
Po-210 concentrations in flue gases at the outlet location averaged
4,492 pCi/dscm (127 pCi/dscf) for the four test runs. On an activity per
gram of particulate basis, Po-210 activity for the outlet runs averaged
55.3 nCi/g PM.
Pb-210 concentrations in flue gases at the outlet location were at or
near the minimum detection limit and averaged 15.0 pCi/dscm
(0.426 pCi/dscf). On an activity per gram of particulate basis, Pb-210
activity averaged 0.200 nCi/g PM. Although the Pb-210 results were more
variable between the two outlet stacks, the results agree within the lower
analytical precision found for results at or near the minimum detection
limit.
3.2.2 Estimated Venturi Scrubber Efficiencies - Method 111
Table 3-18 summarizes the estimated removal efficiencies of the venturi
scrubber control system for removal of particulate, Po-210, and Pb-210 at
test condition B. Removal efficiency was estimated based on the average
inlet results from runs 3 and 4 and the measured outlet results. There were
no inlet measurements performed during test condition B. The outlet values
at the two locations are combined as if the emissions were combined to a
single stack to yield a single concentration. Estimated removal efficiency
for PM was consistent for all the runs, averaging above 92 percent. The
scrubber was estimated to remove less than 20 percent of the inlet Po-210
for all three runs. Estimated removal of Pb-210 across the scrubber
was consistently high, with removal efficiencies from 85.3 to approximately
100 percent.
3.2.3 Front/Back Half Distribution of Emissions in MM 111 Trains
Table 3-19 presents a summary of the distribution of emissions as
collected in the MM 111 sampling trains during test condition B. As seen in
the table, approximately 99.5 percent of the Po-210 collected was present in
the front half of the train. This percentage was consistent for samples
collected at both outlet locations.
JES/045 3-31
-------
TABLE 3-18. ESTIMATED REMOVAL EFFICIENCIES FOR PM, Po, AND Pb,
VENTURI PRESSURE DROP = 6.5 in. W.C., CALCINER 1
OFFGASES, FMC-POCATELLO, IDAHO (August 1988)
Concentration
Inlet'
Outlet1
Removal
Efficiency
Run 5
Particulate (gr/dscf)
Po-210 (pCi/dscf)
Pb-210 (pCi/dscf)
0.4755
134.7
5.526
0.03362
108.7
0.8112
92.93
19.29
85.32
Run 6
Particulate (gr/dscf)
Po-210 (pCi/dscf)
Pb-210 (pCi/dscf)
0.4755
134.7
5.526
0.03776
144.2
7.965E-05
92.06
-7.05^
99.998
Run 7
Particulate (gr/dscf)
Po-210 (pCi/dscf)
Pb-210 (pCi/dscf)
0.4755
134.7
5.526
0.03548
128.7
0.4656
92.54
4.47
91.57
Inlet concentration assumed is the average of results from runs 3 and 4.
Outlet concentration is the average of both stacks weighted for the
different flows from each stack.
cRemoval efficiency calculated assuming that the inlet concentration does
not change with flow rate (i.e., the inlet concentration remains constant
and the inlet gas flow rate is adjusted to equal the total outlet gas flow
rate).
If the removal efficiency is less than zero, the inlet and outlet
values should be considered equal taking into account the precision
of the sampling and analytical methods. The removal efficiency should
be considered zero.
JES/045
3-32
-------
TABLE 3-19. SUMMARY OF FRONT/BACK HALF DISTRIBUTION OF EMISSIONS:
MM 111 SAMPLING TRAINS, PRESSURE DROP = 6.5 in. W.C.,
CALCINER 1 OFFGASES, FMC-POCATELLO, IDAHO (August 1988)
Location Parameter Front Half Back Half
Outlet Particulate 100a NAb
Po-210 99.5 0.5
Pb-210 98.4° 1.6C
aOn average, 85 percent of the particulate matter collected at the outlet was
found on the filter, and 15 percent was collected in the probe and nozzle.
bNA = Not applicable. The addition of 0.1 N HN03 in the impingers prevented
drying and weighing of the impinger catch.
°Results from outlet B, run 5 only. For two samples, all of the Pb-210
activity was in the front half, for two samples, all of the Pb-210 activity
was in the back half, and for one sample, no Pb-210 activity was detected
in either fraction.
JES/045 3-33
-------
The distribution for Pb-210 was very inconsistent between the runs and
the outlet locations. In only one sample was Pb-210 activity detected in
both the front and back half fractions; for that sample, 98 percent of the
activity was in the front half. For two samples, all of the detected Pb-210
activity was in the front half, while in two other samples, all of the
measured activity was in the back half. For one other sample, no activity
was detected in either fraction.
The distribution of PM between the front half fraction components was
evaluated for the samples for condition B. As stated in the footnotes to
Table 3-19, an average of 85 percent of the PM at the outlet was on the
filter and 15 percent was in the probe and nozzle rinses.
JES/045 3-34
-------
4.0 SAMPLING AND ANALYSIS
This section describes specific sampling and analysis activities
performed during the August 1988 test program at the FMC facility. As
described in the Executive Summary of this document (see Table 1-2),
emission samples were collected during periods of two separate scrubber
operating conditions. At a pressure drop across the venturi of 10.5 in.
H20, four test runs were conducted at the venturi scrubber inlet and each of
the two outlet stacks to collect particulate matter and particulate size
samples for subsequent radionuclide analysis. An additional three runs were
conducted at a venturi scrubber pressure drop of 6.5 in. H^O. Particulate
matter and radionuclide samples were collected at the scrubber outlets only.
The following subsections describe the sampling locations at the FMC
site (Section 4.1), the sampling procedures to be used (Section 4.2), the
approach utilized for recovering and analyzing each of the collected samples
(Section 4.3), and the sample custody procedures (Section 4.4).
4.1 SAMPLING LOCATIONS
Figure 4-1 identifies each of the sampling locations for the FMC test
program. The following subsections present descriptions of each of these
locations.
4.1.1 Scrubber Inlet
As seen in Figure 4-1, the scrubber inlet sampling location was
downstream of the calciner just prior to the point where the offgas stream
is split into the two parallel streams feeding the venturi scrubbers.
The sampling was performed in a vertical duct which was rectangular with
dimensions of 10 by 13 ft. (3.05 by 3.96 m). A schematic of the inlet
sampling location is shown in Figure 4-2. The sampling location was
JES/045 4-1
-------
Sampling Locations
GO
O
-Pfc
tn
0
UD
d]
("5]
Ore LJJ
Rn/ii lot
Feed
Ore
Feed
Outlet Stack No. 1-1
Outlet Stack No. 1 -2
Scrubber Inlet
Process Feed
i — Fuel
*• Calciner No. 1
0
Offgases
I
Product to
Reducing Furnace
i — Fuel
• n i k 1 /
* Calciner No. -
2
Offgases "
Product to
Reducing Furnace
H
IS. XJ \x^-^v
Venturi
lx^ "XJ
No. 1-1
N" s\
Venturi
Ix "\j
No. 1-2
r^ ^i
Venturi
\^ ^sj
No. 2-1
N^ ^]
Venturi
^ ^s
; /Outlet\
u--rr W i-i/
I.D. X._JX
Fan [B]
\No. 1-2/
I.D. N^ ^/
Fan
^TT \NO. 2-iy
Fan
/OutletX
*—T* Ulo. 2-2/
I.D. ^^SJ
Calciner #2
and associated
Control Equipment
is not currently
in operation.
Projected
operation date:
October 1988.
No. 2-2
Fan
Figure 4-1. Schematic showing sampling locations at the FMC
calcining operation and pollution control system
cc
CN
ID
-------
m
oo
o
-P»
en
CO
f
•^ Gas Flow Splits
s^-* to Scrubber Modules
i
~7.
i
j
~2
5ft
Dft
!
Sampling
Ports
V
Gas Flow
from Calciner
Side View
o o o o o o o
Gas Flow
Front View
-~13 ft »•
11 II U 11 U U 11
Top View
T
~10ft
oc
CO
CD
Figure 4-2. Schematic of the inlet sampling location at FMC
-------
recognized as a nonideal location due to flow disturbances both up and
downstream. During each MM 111 test run the maximum number of traverse
points were sampled in order to minimize the effect of these disturbances on
sample representativeness. The EPA Method 1 criterion specified a maximum
total of 49 traverse points, 7 in each of the 7 ports.
4.1.2 Outlet Stacks
Controlled flue gases from each calciner unit are discharged to the
atmosphere through two separate scrubber stacks. Outlet sampling was
performed at each of the two stacks. A schematic showing dimensions of the
two similar outlet locations is shown in Figure 4-3. The diameter of the
circular stacks was 76.5 inches. The outlet sampling location ports were
ideal as defined by EPA Method 1 criteria, with each stack requiring
12 traverse points, 6 from each port. The outlet stacks were reduced in
total height by 25-30 ft from their original design due to corrosion
problems. The current stacks are scheduled for replacement in October 1988.
4.1.3 Process Feed Sampling Location
Phosphate rock feedstock (briquettes) was collected from a moving belt
just prior to the vibrator feed conveyor just prior to where the briquettes
were discharged onto the moving grate.
4.2 SAMPLING PROCEDURES
EPA reference sampling methods were used during this test program to
collect flue gas samples for particulate matter and particulate size
distribution. These particulate samples were analyzed for radiation from
radionuclides, specifically polonium-210 and lead-210. EPA reference
sampling methods were also used to measure stack gas velocity/volumetric
flow, moisture content, and molecular weight.
Each sampling method used during the test program is described in
detail in the following subsections.
JES/045 4-4
-------
m
oo
o
-u
en
Sampling
Ports
~25 ft
(T
3
r-
Figure 4-3. Schematic showing one of the two similar outlet sampling locations at FMC
-------
4.2.1 Participate Matter and Radionuclides - Modified EPA Method 111
Particulate matter in both the inlet and outlet streams was collected
using a modification of EPA Method 111. For reference purposes, EPA
Method 111 is included in Appendix A of this document. The specific
modifications included:
o use of 0.1 N HN03 in the impingers instead of water;
o insertion of an extra impinger (empty) following the filter and
heater box (due to the high moisture content of the streams); and
o modification in recovery procedures (discussed in Section 4.3).
A schematic of the Modified Method 111 (MM 111) train that was used in
this test program is shown in Figure 4-4. Flue gas was pulled from the
stack through a stainless steel nozzle and a glass-lined probe. Particulate
matter was removed from the gas stream by a glass fiber filter housed in a
Teflon® sealed. The glass filter holder was maintained at 120 + 14°C
(248 + 25°F). The filter holder contained a Teflon®-coated stainless steel
screen to support the filter. After the heated filter box, an empty
knockout condenser was used to remove excess moisture, followed by two
impingers containing 0.1 N HNO,, another empty knockout condenser, and a
silica gel impinger.
4.2.2 Particle Size Distribution - Andersen MK III
Particle size distribution (PSD) measurements at both the inlet and
outlet locations were made using in-stack Andersen MK III cascade impactors,
equipped with right angle preseparators used to turn gas stream. The
Andersen MK III impactor is an eight-stage cascade impactor which classifies
particles according to their aerodynamic diameter. No buttonhook nozzles
were used.
An example of the sampling train is shown in Figure 4-5. Many of the
components are similar to those used in EPA Method 5 sampling. Stack gas
velocity and temperature profiles were obtained from pretest stack gas
JES/045 4-6
-------
o
-P»
en
L/ Heated
/f Area
Thermocouple^ [\ Probe
•S-TypePltot4^
Thermometer
Filter
Holder
Thermocouple
f Check Valve
Silica Gel
(300 grams)
0.1 N HNO, x Knockout
Manometer Knockout
Stack Wall
Pltot
Thermocouples
Orifice
Air-Tight
Pump
Vacuum Line
Figure 4-4. Schematic of the Modified Method 111 Sampling Train
-------
m
to
o
-n.
en
00
Andersen
Mark III
Y*" Diameter
Steel Pipe Probe
Check Valve
Manometer
DC
O
Figure 4-5. Schematic of the Andersen MK III Cascade Impactor Train
-------
traverses conducted at each sampling location prior to the particle size
measurements. Based on the resulting profile data, two points that were
representative of the stack gas velocity and temperature profile were
selected for collecting the PSD sample. For each test run (both inlet and
outlet), all traverse points were selected from a single port. Subsequent
test runs were sampled using similar point selection criteria; although
points were selected from the opposite port. Stack gas moisture content was
based on data from the preceding MM 111 test runs. Sampling train flow
rates were maintained at constant rates and were selected to optimize the
particle size definitions for the lower size ranges (less than 2 microns).
The goal of each PSD run was to achieve isokinetic sampling (100 + 20%) and
to achieve good size separation in the less than 2 microns particle size.
Due to the high moisture content at each of the outlet sampling
locations, both the preseparator and the impactor were pre-heated above the
flue gas dew point temperature prior to testing. During the test run,
heating was accomplished by wrapping the impactor with heating tape,
insulating the impactor body and waterproofing the entire assembly.
Impactor temperatures during the test runs were maintained above the stack
gas dew point using a variac to regulate electrical current to the heat
tape. Impactor outlet temperatures were monitored and recorded throughout
each run with a type K thermocouple. A condenser system was used to remove
moisture and deliver dry gas to the metering system. Rieve Angel 934 AH
glass fiber substrates were used to collect the samples. The final filter
(back-up filter) met the requirements of ASTM Standard Method D (99.95%
collection efficiency on 0.3 micron dioctylphthalate particles).
Preliminary PSD samples were collected at each location to determine
and establish proper sampling collection parameters. These preliminary
samples were evaluated for evidence of particle bounce, reentrainment,
overloading or underloading. Based on analyses of these preliminary test
runs, sampling rates and durations were established for each of the
subsequent test runs.
JES/045 4-9
-------
4.2.3 Flue Gas Volumetric Flow Rate - EPA Method 2
The volumetric stack gas flow rate for both stack outlet and inlet
locations was determined using procedures described in EPA Method 2. Based
on this method, the volumetric flow rate is determined by measuring the
cross-sectional area of the stack and average velocity of the flue gas
through this cross-sectional area.
The average velocity of the flue gas was calculated from the average
gas velocity pressure, the average flue gas temperature, the wet molecular
weight, and the absolute static pressure. Pressure and temperature profiles
were obtained by traversing the stack.
Pressure and temperature profiles were obtained by an S-type pitot tube
and type K thermocouple at each of the traverse points. An inclined oil
manometer was used to measure pressure differential across the S-type pitot
tube. A calibrated aneroid barometer was used to obtain barometric
pressure. Static gas pressure was measured by an S-type pitot tube with the
face aligned at right angles to the gas stream flow. One side of the pitot
was disconnected after proper placement and static pressure determined using
an inclined manometer.
4.2.4 Flue Gas Molecular Weight Determination - EPA Method 3
The molecular weight of the flue gas at each location was determined
during each MM 111 run using a single point grab sample collected in Tedlar®
bags. The molecular weight analysis was performed using Orsat procedures as
described in EPA Method 3.
4.2.5 Flue Gas Moisture Content - EPA Method 4
The moisture content of the flue gases at both the stack outlet and
inlet locations was determined using procedures described in EPA Method 4.
Based on this method, a known volume of particulate-free gas is pulled
through a chilled impinger train. The quantity of condensed water is
gravimetrically determined and then related to the volume of gas sampled.
JES/045 4-10
-------
The moisture content of the flue gas was determined simultaneously
during the operation of the MM 111 trains. The impingers used with these
trains were weighed before and after sampling. The mass increase in
moisture was related to the volume of gas sampled to calculate the moisture
content of the flue gas.
4.2.6 Process Feed Samples - Composite Grab
Grab samples of the shale briquette feedstock were collected
periodically during each MM 111 flue gas sampling period. The samples were
collected from the vibrator feed conveyor assembly just prior to discharging
into the kiln. Approximately 1 kg (2.2 Ibs) of sample was collected in each
grab. At the end of each flue gas sampling period, the grab samples were
combined, mixed and quartered. A single 1 kg (2.2 Ibs) composite grab
sample corresponding to each sampling period was retained for radionuclide
analysis.
4.3 SAMPLE RECOVERY AND ANALYSIS
4.3.1 Particulate Matter and Radionuclides
Upon completion of each test run, the MM 111 trains were leak checked,
disassembled and filter and impingers were transported to the on-site
recovery trailer. The inlet probes and nozzles were recovered at the
sampling platform, due to the probe length (15 ft). Care was taken to
reduce sample contamination to the extent possible under the conditions
encountered. The outlet probes and nozzles were recovered in the laboratory
trailer.
Openings on each of the disassembled sampling train components were
covered with Teflon® tape or parafilm® prior to transporting to the recovery
site. As soon as possible after completion of the testing, the trains were
recovered. The MM 111 recovery and analytical scheme is shown in
Figure 4-6. The modifications from EPA Method 111 are as follows:
o the back half of the sampling train (impingers) were recovered
for subsequent radionuclide analyses;
JES/045 4-11
-------
Front Half Sample Recovery Fractions
I Back Half Sample Recovery Fractions
Nozzle, probe, cyclone,
brush/rinse
Filter
Evaporate;
dessicate; weigh;
1st, 2nd, 3rd, 4th, Impingers
contents and rinses
Add 16 M HN03
to residue
and digest
Transfer residue in
acid solution to teflon
beaker containing filter
and 0.1N nitric rinse
Digest with 30 ml
29 M HF and heat to
near dryness. Repeat
digestion as necessary
Add 100 ml 16 M HNO3
acid. Digest.
Evaporate to
near dryness
Add 50ml 16 M
HNO3, heat to 85 °C
Reduce volume
to ~20 ml
by heating
Evaporate to
near dryness
Add 50 ml 16 M
HNO3, heat to 85 °C
5th Impinger
(silica gel)
Weigh and
discard
4 Field 4
I Recovery |
I Laboratory 1
1 Analysis 1
Add 10ml 12 M
perchloric acid
and heat
Adjust sample to
known volume (250 ml)
using 3 M HCI
Add 10ml 12 M
perchloric acid
and heat
Adjust sample to
known volume (250 ml)
using 1 M HCI
Analysis for Po-210
by alpha spectrometry
and Pb by beta
and gamma counts
Analysis for Po-210
by alpha spectrometry
and Pb by beta
and gamma counts
Figure 4-6. Modified Method 111 Recovery and Analysis Scheme
a:
in
CO
CO
CM
CO
co
JES/045
4-12
-------
o the front half (probe and filter holder) acetone rinses were
followed by rinses with 0.1 N HNCL; and
o radionuclide analyses were performed separately for front and back
half train fractions. Front half consisted of both the filter and
the probe, nozzle and filter holder rinses; back half consisted of
impinger contents and rinses.
Train recovery and gravimetric determinations were performed by Radian.
The gravimetric determinations were done on-site for the filter and probe
rinse acetone (PRA) components of the sampling train. For each of the
MM 111 trains, samples for radionuclide analyses were sent to EERF in four
components. These four components are listed in Table 4-1. During the
analytical digestion procedures the front half rinses (PRN) were combined
with the dried acetone rinses (PRA) and both were combined with the filter
(F) to provide a front half analysis. Radionuclide analyses were performed
separately for front and back half train catches. The specific analytical
protocol used by EERF for radionuclide analysis is included in Appendix B.
4.3.2 Particulate Size Distribution and Radionuclides
Upon completion of each test run, the impactors were removed from the
duct, oriented vertically and purged for approximately 10 minutes to prevent
water condensation in the impactor assembly. The nozzles were loosely
covered with aluminum foil or Teflon® tape and the impactor placed in a
vertical position where it would not be bumped. After the impactors had
cooled, they were transported to the field laboratory for recovery.
Each stage was inspected for particles that might have accumulated on
surfaces other than the stage collection substrate. By convention, any
particles lost to surfaces upstream of a stage substrate were added to that
substrate's catch. A camel hair brush was used to clean the surfaces.
The substrates were removed from the impactor and placed in their
respective petri dishes using a flat-ended set of forceps and flat-bladed
spatula. Particles from the preseparator were brushed onto the first stage
collection substrate.
JES/045 4-13
-------
TABLE 4-1. MODIFIED METHOD 111 SAMPLING TRAIN COMPONENTS TO BE SENT
TO EERF FOR RADIONUCLIDE ANALYSIS, FMC-POCATELLO, IDAHO
(August 1988)
Container/Component Code Description
Component Number 1 F Filter
Component Number 2 PRA Acetone rinses of nozzle, probe,
and front half of filter holder
Component Number 3 PRN Nitric rinses of probe, and
front half of filter holder
Component Number 4 IR Nitric acid rinses of back half
of filter holder, filter support;
and first, second, third, and
fourth impinger contents and
rinses
JES/045 4-14
-------
After each test run, the substrates were closely examined to determine
if the selected operating conditions were effective. The following criteria
were used to determine if the test run was valid:
o no signs of particle bounce or reentrainment,
o no signs of overloaded deposits or secondary deposition,
o dry filters with no condensed water, and
o minimal particle catch (approximately 2-5 mg per lower stages).
Both reentrainment and overloaded deposits are typically characterized by
increased internal losses to the inner surfaces of the impactor. When
reentrainment and/or overloading occur, primary depositions (from impaction)
are ill-defined and secondary deposition is evident around the primary
deposits. Particle deposition on the substrate should be due to impaction
only. Consequently, when reentrainment and/or overloading do not occur,
deposits are uniform and well-defined (conical) with no evidence of
disturbance. The collected particle size samples were uniform and well-
defined.
Impactor recovery and gravimetric determinations were performed in the
field by Radian. For each of the Andersen impactor trains, samples for
radionuclide analyses were sent to EERF in six components. These six
components are listed in Table 4-2. Radionuclide analyses were performed on
each of these components separately. Analytical digestion procedures were
identical to those described in Figure 4-6 for the MM 111 filters. The
specific analytical protocol used by EERF for radionuclide analysis is
included in Appendix B.
4.3.3 Analytical Errors in Radionuclide Measurements
The measurement errors associated with the radionuclide analysis for
individual samples are shown in Appendix L. The results of duplicate and
intercomparison samples are shown in Section 5.0, Tables 5-6 and 5-10.
Measurement errors for polonium-210 analyses, as shown in Appendix L, were
less than 10% at the 95% confidence level.
JES/045 4-15
-------
TABLE 4-2. ANDERSEN IMPACTOR SAMPLING TRAIN COMPONENTS FOR RADIONUCLIDE
ANALYSIS, FMC-POCATELLO, IDAHO (August 1988)
Container/Component
Code
Description
Component Number 1
Component Number 2
Component Number 3
Component Number 4
Component Number 5
Component Number 6
PSD-1
PSD-2
PSD-3
PSD-4
PSD-5
PSD-6
Preseparator Stages 0 and 1
Stages 2, 3, 4, and 5
Stage 6
Stage 7
Stage 8
Stage 9 (back-up filter)
JES/045
4-16
-------
Measurement errors for lead-210, as shown in Appendix L, were
relatively large (i.e., greater than 50%) with many of the samples near or
below the detection level (i.e., errors of greater than 100%). The large
errors in the lead-210 measurements were due to the low concentration of
lead-210 in the sample aliquot analyzed. As shown in Apepndix B, lead-210
and polonium-210 were analyzed simultaneously from the same sample aliquot.
The sample aliquot size was determined by the polonium-210 content of the
sample. For the FMC plant, the lead-210 content of the samples was
relatively low compared to the polonium-210 content; therefore, this
resulted in very low amounts of lead-210 in the sample aliquot.
4.3.4 Reporting of Lead-210 Data
The large errors associated with the lead-210 measuremnets present some
problems in reporting, averaging, and summarizing this data. In presenting
the data in this report, the following procedure was used. For all values
greater than zero, the actual measured value was reported (even if the error
was greater than 100%). However, values with errors greater than 100% at
the 95% confidence level were identified as non-detectable in the summary
tables. Negative values (i.e. values less than zero) were reported as 0.00
in the summary tables. The 0.00 values were used in determining average and
sum total values. This procedure will results in a small positive bias in
the data.
Because of the large uncertainties associated with the lead-210 data,
any interpretation of the data should taken into consideration the high
degree of uncertainty in these measurements.
4.4 SAMPLE CUSTODY
Sample custody procedures followed during this program were based on
EPA recommended procedures. The custody procedures emphasized careful
documentation of sample collection and field analytical data and the use of
chain-of-custody records for sample being transportation. The team leader
for the field testing effort was Mr. R. F. Jongleux. The team leader was
JES/045 4-17
-------
responsible for ensuring that proper custody and documentation procedures
were followed for the field sampling and field analytical efforts.
A master sample logbook was used to document all sample collection
activities (Notebook #21088). All sampling data, including information
regarding sampling times, locations, and any specific considerations
associated with sample acquisition were recorded on preformatted data
sheets.
Following sample collection, all samples were given a unique
alphanumeric (Radian) sample identification code. Figure 4-7 contains an
example of the alphanumeric ID codes and abbreviations used for the FMC
samples. Sample labels and integrity seals were completed and affixed to
the sample container. As the samples were packed for shipment,
chain-of-custody forms were completed for each shipment box specifying
treatment of the samples.
JES/045 4-18
-------
o
-I*
in
FMC-082388-MM111-IIM-1-F
/
Plant:
Data:
Sampling Method:
Modified Method 111
PSD = Particle Size
Distribution
GR = Grab
Sampling Location:
Inlet
OTA = Outlet 1-1
OTB = Outlet 1-2
Run: Sample Fraction:
Filter
PR = Probe Rinse
IR = Impinger Contents
and Rinses
ST1 = PSD Stage 0,1 and
Preseparator
ST2-5 = PSD Stages 2,
3, 4, and 5
ST6 = PSD Stage 6
ST7 = PSD Stage 7
ST8 = PSD Stage 8
ST9 = PSD Stage 9
(Back-up filter)
Figure 4-7. Example of alphanumeric ID codes for the FMC test program
-------
5.0 QUALITY ASSURANCE AND QUALITY CONTROL (QA/QC)
Specific quality assurance and quality control procedures were
incorporated into the FMC test program to ensure the production of useful
and valid data. The overall quality assurance/quality control (QA/QC)
objective was to ensure precision, accuracy, completeness, comparability,
and representativeness for each parameter measured in this test program.
The QA/QC procedures and results described in this section represent an
integral part of the overall sampling and analysis scheme. The acceptance
criteria, control limits and corrective action that were used for the test
program and the results achieved are summarized in Table 5-1.
Section 5.1 presents QA/QC results for the particulate and PSD sampling
activities, Section 5.2 presents QA/QC results for radionuclide analysis,
and Section 5.3 presents QA/QC results for particulate analysis.
5.1 QUALITY ASSURANCE/QUALITY CONTROL FOR SAMPLING AND RECOVERY
The isokinetic results for the modified Method 111 (MM 111) and
particle sizing sampling trains are summarized in Tables 5-2 and 5-3,
respectively. Of the 27 PSD and MM 111 sampling trains operated, two MM 111
trains did not meet the QA/QC isokinetic objective of 100 + 10 percent. For
the MM 111 sampling trains, the isokinetics for Inlet-run 1 and Inlet-run 2
were 119.2 and 118.8, respectively. The high isokinetic values were due to
an error in the nozzle diameter measurement. The error was not discovered
until after the runs were completed. Thus, an additional run was conducted
at all locations to ensure representative data.
The leak check results for the MM 111 and particle sizing sampling
trains are summarized in Tables 5-4, 5-5 and 5-6. All of the final leak
rates met the QA/QC leak rate criteria of less than 0.02 acfm for the
particulate sampling trains. Particle size operating procedures dictate
JES/045 5-1
-------
TABLE 5-1. SUMMARY OF ACCEPTANCE, CRITERIA, CONTROL LIMITS
AND CORRECTIVE ACTION AND ACHIEVED RESULTS
Criteria
Particulate Sampling
Isokinet ics
- Method 111
Particle Size
Control Limits
100 + 10%
100 + 20%
Achieved (%)a
88b
100
Corrective Action
Performed additional test run.
Final leak rate (after
each port)
Dry gas meter calibration
Individual correction
factors ( -y.)
Average correction factor
Nozzles
Radionuclide Analysis
Duplicate analysis
Performance standards
Analytical reagent blanks
Yield
< 0.02 acfm or 4%
of sampling rate,
whichever is less
Post average factor C")0
agree + 5% of prefactor
Agree within 2% of
average factor
1.00 + 1%
Any two diameters should
agree within 0.004 inches
80% should agree within 2(7 as
determined in EPA 620/5-82-012
90% should agree within 2(7 as
determined in EPA 620/5-82-012
Below MDLC
50%
100
100
100
100
100
88
93
91
None required, criteria met.
None required, criteria met.
None required, criteria met.
None required, criteria met.
None required, criteria met.
Re-run sample, check reagents and
procedure.
Re-run sample, check reagents and
procedure, JMW 88.5355 rerun.
Check reagents and glassware.
Re-run low yield samples to confirm
yield and results. Twenty-two
percent of the low yield samples
were re-analyzed to confirm results.
Time constraints limited the number
of reruns.
Percentage represents fraction of test runs for which the QA objective was achieved.
Additional test runs were conducted to meet the quality objective, however, only two Method 111 inlet trains
were within the isokinetic QA requirements.
CThe minimum detectable level calculated for Po-210 was 1.2 pCi/analyses and for Pb-210 was 1.7 pCi/analysis.
JES045
-------
TABLE 5-2. SUMMARY OF ISOKINETIC RESULTS FOR MODIFIED METHOD 111 SAMPLING
TRAINS, FMC-POCATELLO, IDAHO (August 1988)
Run Date
1 8/24/88
2 8/24/88
3 8/25/88
4 8/25/88
5 8/26/88
6 8/26/88
7 8/26/88
Location
Inlet
Outlet A
Outlet B
Inlet
Outlet A
Outlet B
Inlet
Outlet A
Outlet B
Inlet
Outlet A
Outlet B
Outlet A
Outlet B
Outlet A
Outlet B
Outlet A
Outlet B
Isokinetics (%)a
119. 2b
97.9
92.7
118. 8b
94.5
93.6
104.2
94.2
99.3
99.3
94.0
97.9
95.7
98.4
98.4
98.1
96.9
98.2
alsokinetic QA/QC objective is 100 + 10%.
blsokinetics did not meet QA/QC criteria.
JES/045 5-3
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TABLE 5-3. SUMMARY OF ISOKINETIC RESULTS FOR PARTICLE SIZING SAMPLING
TRAINS, FMC-POCATELLO, IDAHO (August 1988)
Run Date Location Isokinetics (%) '
8/23/88 Inlet 104.4
Outlet A 100.6
Outlet B 95.8
8/24/88 Inlet 115.8
Outlet A 99.8
Outlet B 103.2
8/19/88 Inlet 112.5
Outlet A 106.0
Outlet B 104.2
alsokinetic QA/QC objective is 100 + 20%.
Flow was maintained at a constant rate.
JES/045 5-4
-------
CO
o
in
TABLE 5-4. SUMMARY OF LEAK CHECK RESULTS FOR THE OUTLET MODIFIED METHOD 111 SAMPLING TRAINS,
CALCINER 1, FMC-POCATELLO, IDAHO3 (August 1988)
Initial - 1st Port
Run Date
1 8/24/88
2 8/24/88
3 8/25/88
Y1 4 8/25/88
in
5 8/26/88
6 8/26/88
7 8/26/88
Location
Outlet
Outlet
Outlet
Outlet
Outlet
Outlet
Outlet
Outlet
Outlet
Outlet
Outlet
Outlet
Outlet
Outlet
fr
S-
S-
k
>
b
8-
Leak Rate
(acfm)
0.010
0.010
0.016
0.010
0.013
0.010
0.010
0.010
0.011
0.010
0.015
0.010
0.012
0.010
Vacuum
(in. Hg)
5
8
5
9
5
8
5
9
5
9
8
10
6
10
Final - 1st Port
Leak Rate
(acfm)
0.010
NR
0.006
NR
0.010
NR
0.012
NR
0.012
NR
0.020
NR
0.008
NR
Vacuum
(in. Hg)
5
NR
5
NR
5
NR
7
NR
6
NR
8
NR
6
NR
Initial - 2nd Port
Leak Rate
(acfm)
0.010
NR
0.005
NR
0.010
NR
0.008
NR
0.010
NR
0.012
NR
0.006
NR
Vacuum
(in. Hg)
5
NR
5
NR
5
NR
5
NR
5
NR
10
NR
6
NR
Final - 2nd Port
Leak Rate
(acfm)
0
0
0
0
0
0
0
0
0
0
0
0
0
0
.002
.010
.008
.010
.001
.010
.008
.010
.008
.010
.018
.010
.012
.010
Vacuum
(in. Hg)
8
9
5
10
8
9
5
10
5
10
12
10
6
9
aLeak rate QA/QC objective is less than 0.02 acfm or 4 percent of sampling rate, whichever is less.
Values represent leak checks made at the beginning and the end of the test.
NR = Not recorded.
-------
TABLE 5-5. SUMMARY OF LEAK CHECK RESULTS FOR THE INLET MODIFIED METHOD 111
SAMPLING TRAINS, FMC-POCATELLO, IDAHO3 (August 1988)
Run Date
1 8/24/88
2 8/24/88
3 9/25/88
4 8/25/88
Initialb
Leak Rate Vacuum
Location (acfm) (in. Hg)
Inlet 0.010 10
Inlet 0.010 NR
Inlet 0.010 7
Inlet 0.001 6
Finalb
Leak Rate
(acfm)
0.010
0.002
0.010
0.020
Vacuum
(in. Hg)
NR
NR
3
4
Leak rate QA/QC objective is less than 0.02 acfm or 4 percent of sampling
rate, whichever is less.
Values represent leak checks made at the beginning and the end of the
test.
NR = Not recorded.
JES/045
5-6
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TABLE 5-6. SUMMARY OF LEAK CHECK RESULTS FOR PARTICLE SIZING SAMPLING
TRAINS, FMC-POCATELLO, IDAHO (August 1988)
Initial
;ak Rate'
Run Date Location (acfm) (in. Hg)
Leak Ratea Vacuum
8/24/88 Inlet 0.001 NR
Outlet A 0.010 10
Outlet B 0.010 5
8/24/88 Inlet 0.020 10
Outlet A 0.002 NR
Outlet B O.Olo NR
8/25/88 Inlet 0.001 NR
Outlet A 0.020 10
Outlet B 0.008 8
aLeak rate QA/QC objective is less than 0.02 acfm or 4 percent of sampling
rate whichever is less. Only initial leakchecks are performed to prevent
disturbance of the collected particulate on each stage in the impactor.
NR = Not recorded.
JES/045 5-7
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that no final leak check is performed on the impactor because to do so would
dislodge the particles impacted on the individual substrates and bias the
data. Therefore, only pretest leak checks were performed on PSD trains.
In addition to the isokinetics and the leak check criteria, the
following QA/QC procedures were satisfied for the purpose of ensuring valid
results:
o All sampling equipment passed a thorough visual and operation
check prior to and after shipment to ensure clean and operable
parts. Equipment which failed to pass this check was not used in
the field.
o Manometers were leveled and zeroed before measuring the pressure
across the S-type pitot tubes.
o The temperature measurement system was capable of measuring the
ambient temperature prior to each traverse to within + 2 C of the
average measured ambient temperature.
o The field personnel reviewed sampling data forms daily on-site
during testing.
o A Modified Method 111 field blank was collected for both the inlet
and outlet locations during the test period to evaluate any
background contamination. This field blank train (FB) was
collected with glassware components that had been previously used
to collect MM 111 samples at that location, and then recovered in
the prescribed fashion. The purpose of the field blanks was to
identify background contamination levels introduced to the sample
from the glassware, recovery solvents, or from handling of the
train and components in the field during typical situations.
o Blanks of filters and reagents were collected and archived.
Filter and reagent blanks have not been analyzed at this time for
radionuclides since field blanks did not contain unacceptable
levels of contamination.
o The trains were assembled and recovered in a laboratory trailer
with a controlled environment which controlled dust contamination.
o Ice was maintained in the impinger baths at all times, exit
temperatures were maintained less than 20 C (< 68 F).
o Any unusual occurrences during testing were noted on the
field data forms or recovery notebooks.
JES/045 5-8
-------
o Sampling nozzles and S-type pi tot tubes were measured and
passed the required inspection.
o The roll and pitch axis of the S-type pi tot tube and the sampling
nozzle were maintained at 90 to the flow during sampling.
o Each leg of the S-type pitot tube achieved the prescribed leak
check criterion described in EPA Method 2.
o The entire sampling train was checked to ensure that the leakage
rate was less than or equal to 0.02 cfm or 4 percent of the
average sampling rate (whichever is less) before and after moves
from one sampling port to another during a run.
o Readings of the dry gas meter, AP, AH, temperature, and vacuum
pump were made during sampling at each traverse point.
o Filters were handled out of drafts and transferred with tweezers.
o Sample trains were disassembled and the samples recovered in clean
areas to prevent contamination.
o The nozzle was capped prior to and following recovery.
o The samples were transferred to appropriate storage containers and
clearly labeled.
o Reagent dispenser bottles were clearly labeled.
o Sampling glassware was routinely rinsed three times with each
reagent to remove all of the sample.
o Reagent lot numbers were recorded.
o All sampling and recovery glassware was capped or covered when not
in use.
o Probe and nozzle brushes, tweezers, and scrapers were rinsed
before use with the proper reagent(s) to minimize any possible
sample contamination.
The particle sizing results were of high quality because the following
QA/QC procedures were implemented and achieved:
o All substrates were desiccated and weighed to a constant weight
(to the nearest 0.05 mg).
o Each impactor stage was visually inspected for proper alignment
and uniform seating by an experienced technician.
JES/045 5-9
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o Preliminary test runs were conducted at each location (inlet and
outlet) to define operating conditions. Substrates from these
runs were evaluated for evidence of particle bounce, or
reentrainment and sampling parameters for subsequent runs were
modified to reflect the necessary corrective actions.
o All impactor stages were visually inspected for proper substrate
peak shape and loading by a qualified, experienced individual.
o The impactor stages were characterized by well-defined, tall
peaks. There was little evidence of particle bounce on the
impactor substrates.
o Impactors at the outlet location were heated and insulated
specifically to prevent moisture condensation on the impactor
substrates. The impactor exit temperature was maintained above
the due point of the flue gas stream. Impactor runs with wet
substrates were rejected if water condensation occurred and
filter substrate recovery was compromised.
5.2 RADIONUCLIDE ANALYSIS QA/QC
Activities with errors greater than 100 percent at the 95 percent
confidence level were considered non-detectable. If these activities were
non-negative, they were used in calculating the flue gas concentrations.
Negative activities were considered equivalent to zero.
During the radionuclide analyses, every tenth sample was analyzed in
duplicate. The duplicate analyses should agree within 2o" and the duplicate
results are presented in Table 5-7- Of the twenty-two duplicate analyses,
seventeen agreed within 10 percent. Five duplicate analyses were above
20 percent. However, these samples contained radionuclides at a relatively
low concentration, indicating that the analysis may be less reliable at very
low concentrations.
In addition, the following QA/QC procedures were satisfied for the
purpose of ensuring valid results:
o Internally prepared performance evaluation samples were analyzed
according to the approved EERF Quality Assurance Plan.
o Externally prepared performance evaluation (if submitted by the
plant) were analyzed along with the samples.
JES/045 5-10
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TABLE 5-7. DUPLICATE RESULTS FOR RADIONUCLIDE ANALYSES AT FMC-POCATELLO, IDAHO (August 1988)
EERF No.
88.
88.
88.
88.
88.
88.
88.
88.
88.
88
88
05910
05920
05940
05950
05930
05860
05870
05880
.05890
.05900
.05960
Run No.
PSD -OTA- 1
Stage 1
PSD-OTB-1
Stage 8
PSD-IN-3
Stage 1
PSD-OTA-3
Stage 8
PSD-OTA-2
Stage 6
OTA-1
OTB-2
IN-4
OTA- 6
OUT-FB
PSD-FB
Analysis 1
(pCi/sample)
104.72
206.54
37.964
360.55
61.783
4716.4
111.27
74.767
6073.8
58.629
0.66465
Po-210
2
-------
o Procedure background counts (analytical reagent blanks) were
determined using analytical reagents, according to the EERF
Quality Assurance Plan.
As described in the previous sections, a field blank was collected at
each of the two sampling locations (inlet and outlet). A field blank is a
complete sampling train that is equipped, prepared, and handled in a manner
identical to those trains used to collect samples. The one difference
between field blank trains and test sampling trains is that the field blank
trains are not inserted into the stack and do not collect sample. The field
blank trains for FMC were prepared using glassware and components previously
used at that location during the test program to collect actual flue gas
samples. The field blank train components were assembled and handled in the
same fashion and recovery environment as the standard sampling train
components. The field blank train components were then recovered using the
same solvents and sample containers as the field samples.
Table 5-8 contains the field blank results from each location. As seen
in the table, radionuclide activities in the inlet field blank were less
than 2 percent of the average activities for that location. At the outlet,
the field blank activities were approximately 1.1 percent for Po-210 and
2.2 percent for Pb-210. These results are within the acceptance criteria
for this program.
5.3 QA/QC RESULTS FOR PARTICLE SIZE SAMPLING
A blank (substrate media interaction) impactor run was performed to
assess the degree of substrate-flue gas interaction. The blank PSD train
was operated for the same time interval as the sample trains. Flue gas
constituents can react with filter materials and, therefore, bias the final
filter weights. Where bias occurs, it may be either negative or positive.
The flue gas interaction with filter substrate materials will be uniform;
that is, it effects all filters not just one or two. This interaction
ideally will be negligible. The criterion for determining if bias exists is
that the average recorded blank substrate weight (loss or gain) should be no
greater than 10 percent of the minimum acceptable substrate weight gain.
JES/045 5-12
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TABLE 5-8. SUMMARY OF MM 111 RADIONUCLIDE FIELD BLANK VALUES FOR THE
TEST PROGRAM, FMC-POCATELLO, IDAHO (August 1988)
Description
Field Blank
Average Test Value
Minimum Test Value
Inl
Po-210
(pCi/train)
73.7761
4,899.86
3,384.03
et
Pb-210
(pCi/train)
0.26874
125.60
81.233
Outl
Po-210
(pCi/train)
62.6236
5,453.93
3,861.22
et
Pb-210
(pCi/train)
3.04937
135.898
27.8096
Field Blank Expressed
as Percentage of
Average Test Value
Field Blank Expressed
as Percentage of
Minimum Test Value
1.51
2.18
0.21
0.33
1.15
1.62
2.24
10.97
JES/045
5-13
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The desired minimum weight gain was 2-5 mg + 0.05 mg per stage. Thus, a
significant weight gain or loss would be 0.2 mg (0.0002 g) + 0.05 mg. The
actual minimum weight gain per stage was less than one milligram.
Substrate interaction impactor runs were performed at both the inlet
and outlet locations. The run was performed identically to a standard run
except that the nozzle of the train was oriented opposite of the flue gas
flow direction and a regular filter (back-up filter) replaced the substrate
on the zero stage. The weight gains for the blank interaction runs are
presented in Table 5-9.
The average net gain was -0.00017 grams for the inlet blank and
0.0166 grams for the outlet blank. The inlet blank is below the weight gain
criteria, indicating that there was no consistent positive or negative bias.
Thus, the variability of the net weights is due to the imprecision of
weighing and substrate handling. However, the outlet blank gain is greater
than the QA criteria. For stages 1-8, since the net gain is distributed
equally between negative and positive, the data indicate no bias but a large
variability. The net gain in stage 9 is significantly positive, possibly
due to a wet substrate. However, since the outlet PSD data correlate well,
this variability may actually be specific to the blank sample. Thus, the
outlet data are considered valid and the PSD data was not adjusted for flue
gas interaction.
5.4 DUPLICATE ANALYSES BY AN INDEPENDENT LABORATORY
Extracts prepared by EERF for four samples were split into two aliquots
and sent to TMA Norcal Laboratories for additional independent analyses.
The samples were analyzed for polonium-210 only by TMA Norcal Laboratories.
The results are presented in Table 5-10. The difference between the
duplicate analyses ranged between 5 to 19 percent, indicating good agreement
between the analyses performed by the two laboratories.
JES/045 5-14
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TABLE 5-9. FLUE GAS INTERACTION SAMPLE WEIGHT GAINS,
FMC-POCATELLO, IDAHO (August 1988)
Sample Weight3
Filter Number (g)
Inlet - Blank
FN-1
FN-2
FN-3
FN-4
FN-5
FN-6
FN-7
FN-8
FN-9
Average (stages 1-9)
Outlet - Blank
FM-1
FM-2
FM-3
FM-4
FM-5
FM-6
FM-7
FM-8
FM-9
Average (stages 1-9)
0.78739
1.39368
0.83817
0.76119
0.78778
0.78148
0.78194
0.75912
0.88943
0.77642
0.76213
0.84928
0.76589
0.78708
0.77119
0.78975
0.76197
0.89464
Tare Weight3
(g)
0.78734
1.39371
0.83828
0.76149
0.78803
0.78173
0.78223
0.75945
0.88942
0.76212
0.84924
0.76580
0.78703
0.77100
0.78960
0.76203
0.89399
0.62824
Net Gainb
(g)
0.00005
-0.00003
-0.00011
-0.00030
-0.00025
-0.00025
-0.00029
-0.00033
0.00001
-0.00017
0.01430
-0.08711
0.08348
-0.02114
0.01608
-0.01841
0.02772
-0.13202
0.26640
-0.0166
Weighed to a constant weight (+ 0.00005 g).
DNet gain should be less than 0.0002 + 0.00005 g to meet the QA criteria.
JES/045
5-15
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TABLE 5-10. DUPLICATE ANALYSES FOR POLONIUM-210
PERFORMED BY AN INDEPENDENT LABORATORY
oico Curies oer samole
EERF No.
88.5659
88.5661
88.5663
88.5665
Run
No.
OTA-2-FH
OTB-3-FH
OTC-3-FH
OTD-3-FH
Analysis 1
(by EERF)
375
652
533
810
Analysis 2a
(by TMA Norcal)
425
689
505
977
Difference
(%)
12.5
5.5
5.4
18.7
aNorcal Po-210 results at analysis (10/4/88) were decayed to collection date
(8/17/88) for comparison with EERF data using this equation.
ACTPo?c = ACTPo0a • e \o -
where:
ACTp ~ = Activity of Po at collection.
ACTp (g = Activity of Po at analysis.
Ap = Radiological decay constant (fraction/day) of Po.
ACTp,- = Activity of Pb at analysis.
Ap. = Radiological decay constant (fraction/day) of Pb.
T = Time between analysis and collection (days). Since no Pb
data was associated with the Norcal data, the EERF Pb data
was decayed to 10/4/88 using the following equation and
entered into the first equation for ACTp. @ .
AQ = Activity on EERF analysis date.
t = Days between EERF analysis and 10/4/88.
JES/045 5-16
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