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PROJECT W-3 14
POLYUREA SPECIAL PROTECTIVE
COATING (SPC) TEST REPORT
CHEMICAL COMPATIBILITY
AND PHYSICAL
CHARACTERISTICS
TESTING
Prepared For
C E M Hill Hanford Group
BY
Robert Mauser, Engineer
Los Alamos Technical Associates, Inc.
Richland, Washington
April 6,2001
RPP-7806,Rev. 0
PROJECT W-314 Polyurea Special Protective
Coating (SPC) Test Report Chemical Compatibility
& Physical Charecteristics Testing
Robert Mauser
CHG
Richland, WA 99352
U.S. Department of Energy Contract DE-AC27-99RL14047
EDT/ECN: 631710 uc:
Cost Center: 7 C 9 0 0 Charge Code:
B&R Code: Total Pages: 106
Keywords: Test Report, Polyurea, waste compatibility, adhesion,
decontamination factor
Abstract: This Engineering Test report outlines the results obtained from
testing polyurea on its decon factor, tank waste compatibility, and
adhesion strength when subjected to a high level of gamma radiation.
This report is used in conjunction with RPP-7187 Project W-314 Pit
Coatings Repair Requirements Analysis, to document the fact polyurea
meets the project W-314 requirements contained in HNF-SD-W314-PDS-005
and is therefore an acceptable SPC for use in W-314 pit refurbishments.
TRADEMARK DISCLAIMER. Reference herein to any specific commercial product, process, or service by trade name,
trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or
favoring by the United States Government or any agency thereof or its contractors or subcontractors.
Printed in the United States of America To obtain copies of this document, contact: Dowment Control Services,
P.O. Box 950, Mailstop H6-08, Richland WA 99352, Phone (509) 372-2420: Fax (509) 376-4989.
M?!FC7
o/
f/?/ APR09 20
Release Approval ’ Date
Approved For Public Release
A-6002.767 (0301)
TABLE OF CONTENTS
Section
Executive Summary 1
Purpose and Scope 2
Polyurea Compatibility with Tank Waste 3
Adhesion Strength 4
Radiological Exposure 7
Decontamination Factor (DF) 9
General Conclusion 11
Compatibility with Tank Waste 1-A
0 Results Spreadsheet 2-A
0 Waste Characterization Sheets 4-A
Adhesion Strength 1-B
0 Results Spreadsheet 2-B
0 Pictures 4-B
Radiological Exposure 1-c
Results Spreadsheet 2-C
0 Pictures 3 -c
Decontamination Factor (DF) 1-D
0 Results Spreadsheet (smooth finish) 2-D
Results Spreadsheet (stippled finish) 15-D
Pictures 28-D
Calibration Spreadsheets 2-E
Testing Contract with PNNL 2-F
Gamma Irradiation 1-G
0 Data Spreadsheet 2-G
0 Calibration Spreadsheets 3-G
Pictures 12-G
Technical References 1-H
RPP-7806 Rev. 0 i
Acronyms
ASTM American Standard Testing Methods
DF Decontamination Factor
DST’s Double Shell Tanks
ECN Engineering Change Notice
RPP River Protection Project
SPC Special Protective Coating
..
RPP-7806 Rev. 0 11
Project W-314
Polyurea Special Protective Coating (SPC)
Test Report Chemical Compatibility
&
Physical Characteristics Testing
Executive Summary
When polyurea was identified as a potential Special Protective Coating (SPC) to replace
the current pit coating and coating practices, an extensive search of formulations and
vendors was conducted to identify a polyurea formulation that could meet the project
requirements. The search included the comparison of specification data sheets of
multiple polyurea formulations from six different vendors. At the time of this search
Envirolastic AR 425' was the only polyurea formulation found that could meet the
project requirements contained in HNF-SD-W3 14-PDS-005 Rev. 3. Because of the
unique chemical and radiological nature of Hanford tank waste, more testing was
required to confirm total compatibility of the SPC with this projects requirements.
This report documents selected testing of a polyurea SPC (Envirolastic AR 425) to
resolve uncertainties in the ability of this SPC to meet project W-314 requirements
identified in RPP-7187, Project W-314 Pit Coating Repair Requirements Analysis. The
tests documented include:
1. Polyurea Compatibility with Tank Waste
2. Adhesion Strength
3. Radiological Exposure
4. Decontamination Factor
The testing documented that polyurea meets project requirements with the exception of
adhesion strength. However, the adhesion strength test provided the basis to modify the
project adhesion strength requirement to a value, which this polyurea formulation meets.
In addition the radiological resistance requirement was determined to be excessive. The
radiological testing performed meets the projects needs and is consistent with the criteria
modifications proposed in this report.
This report identifies the procedures and results from the above testing as well as the
conclusions derived from the results. Adhesion strength testing, radiological exposure,
and decontamination factor testing were all performed on a quantitative level. The
compatibility with tank waste testing was performed to ASTM D 3912 standard;
however, the results are qualitative by nature where precision and bias are not definable.
I
Envirolastic AR 425 is a registered trademark of EnviroChem Technologies.
RF'P-7806 Rev. 0 1
Purpose and Scope
Project W-314, Tank Farm Restoration and Safe Operations, has called for the
implementation of the polyurea SPC Envirolastic AR 425 in pump and valve pits
associated with double shell tanks (DST’s). The polyurea SPC was chosen for its
physical properties, as well as its chemical and radiological resistance. Although the
project has evaluated polyurea extensively, there were some uncertainties related to
compatibility with Hanford tank waste, decontamination factor (DF), resistance to
radiological exposure, and adhesion (pull-off) strength when applied on walls that were
previously coated with Amercoat’. This report documents the testing performed to
resolve these uncertainties, and is associated with RPP-753 1, project W-314 Polyurea
Special Protective Coating (SPC) Test Plan Chemical Compatibility and Physical
Characteristics Testing. This report also describes the testing methods, procedures,
results, and conclusions drawn from the results. The four areas of additional testing and
the rationale for each, are discussed below:
1. Polyurea Compatibility with Tank Waste - Chemical compatibility data sheets
supplied by the vendor of Envirolastic AR 425 documented the polyurea
formulation could handle a caustic environment (pH 14) through their testing of
the polyurea against 50% NaOH. Therefore, chemical compatibility testing was
undertaken using tank waste to determine if the polyurea formulation met the
other chemical resistance requirements documented in HNF-SD-W3 14-PDS-005,
Project Development Specification for Special Protective Coating, Revision 3,
September 28, 2000. Samples in this testing series were immersed in supernatant
liquid waste from two Hanford waste tanks at ambient temperatures.
2. Adhesion Strength -Adhesion strength testing of polyurea was conducted to
determine two things: first, did it meet the minimum pull-off strength
requirements documented in HNF-SD-W3 14-PDS-005 Project Development
Specificationfor Special Protective Coating, Revision 3, September 28, 2000 and
second, if through testing, could a basis be established for a lower pull-off
strength requirement? The testing was conducted on twelve concrete samples
which had undergone various levels of surface preparation to determine the
minimum amount of surface preparation required on a concrete surface previously
coated with Amercoat.
3. Radiological Exposure - Though radiation exposure data existed for some
formulations of polyurea indicating that it met the project’s requirements, there
was however, no radiation exposure data on the Envirolastic AR 425 product
selected by the project. It was anticipated that the Envirolastic AR 425
formulation would be more radiation tolerant than the earlier tested formulations
due to its higher degree of polymer cross-linking.
’Amercoat is a registered trademark of Ameron Corporation.
RPP-7806 Rev. 0 2
The radiation tolerance testing was therefore performed to determine two things:
first, does any significant adhesion changes result from exposure to 1 .0 X 1O of
'
R
Gamma radiation and second, are there any physical changes in the polyurea
noted by visual examination after exposure to 1.O X 10'R of Gamma radiation?
4. Decontamination Factor - Though decontamination factor data existed for some
formulations of polyurea indicating that it was close to meeting the project's
requirements. There was no decontamination factor (DF) data on the Envirolastic
AR 425 product that had been selected by the project. The decontamination
factor testing was undertaken on the Envirolastic AR 425 product to determine if
this formulation met the requirement in HNF-SD-W314-PDS-005 Rev. 3.
POLYUREA COMPATIBILITY WITH TANK WASTE
Procedure
This testing was performed to verify compatibility of polyurea SPC with Hanford tank
waste. It was conducted in accordance with ASTM 3912-80 section 6.3.1.1, Standard
Test Method for Chemical Resistance of Coatings Used in Light- Water Nuclear Power
Plants as required by project W-314 SPC PDS.
Four polyurea coated carbon steel plates approximately 3" X 2" X %" were used for this
test. There were two colors used for the purpose of sample differentiation. Two coupons
(a gray color and a black color) were immersed in supernatant waste from tank 241-AP-
101. Two other coupons (a gray color and a black color) were immersed in supematant
waste from tank 241-BY-106. The supernatant waste from tanks 241-AP-101 and 241-
BY-106 were chosen as they were available for use and are representative of liquid waste
that is found in Hanford waste tanks. The procedure followed ASTM D 3912-80 section
6.3.1.1 with the following additions:
The test coupons were immersed in solution on 1/26/01 at 4: 15 PM, and the first
analysis occurred on 1/29/01 at 8:40 AM, with additional analyses to occur on
successive days after each 24 hr period for a total o f 5 evaluations. This testing
was performed in the hot cells located at 2 2 2 4 Laboratory. The first inspection,
at 8:OO AM on 1/29/01, came 64 hours after initial immersion (1/26/01 at 4:15
PM) with subsequent inspections following the ASTM D 3912 procedure. The
initial time period of 64 hours, differs from the ASTM procedure of24 hours, due
to time constraints on the project and the availability ofhot cell personnel. This
longer than required initial exposure is more stringent than required and therefore,
provides bounding results.
A plastic forceps tool was used within the hot cell with robotic manipulator arms
to attempt to mar the polyurea surface to see if any softening had occurred after
every 24 hr period.
RPP-7806 Rev. 0 3
ASTM D 3912 procedure for a simulated exposure to occasional splash and spillage, calls
for the test coupons to be immersed in the chemicals for a period of 5 full 24-hour
periods. At the end of each 24-hour period the samples were to be removed from the
immersion and visually inspected for color changes, blistering, delamination, peeling, and
softening. This testing is qualitative by nature where precision and bias are not defined.
In addition to the ASTM testing, four test coupons were immersed in supernatant liquid
from tanks 241-AP-101 and 241-BY-106 for a period of 90 days. After the initial
compatibility testing which lasted only 30 days with inspections occurring weekly, the
testing was continued through the full 90 days as a more stringent test of the polyurea
SPC than was required by ASTM D 3912. Because the period of immersion in this
process was longer than that required by ASTM protocols, the results show the
Envirolastic AR 425 product substantially exceeds the ASTM requirements.
Results
Visual inspections were performed on each test coupon to determine if the coating had
experienced any color changes, blistering, peeling, or delaminating. Inspection for
softening involved the use of a plastic forceps tool. This tool was used to attempt to
scratch, mark, or dent the polyurea. At no time during the examination periods, was there
any indication that the polyurea was affected by the chemicals that make up the tank
waste. The scratch tests indicated that no softening of the coating had occurred.
See appendix A.
After the last inspection, the coupons were compared with test coupons that had no tank
waste exposure. There was no difference visually detected between the exposed and the
unexposed test coupons.
Conclusion
Waste compatibility testing disclosed no incompatibilities or adverse impacts on the
polyurea test coupons from prolonged exposure to Hanford tank waste.
ADHESION STRENGTH
The purpose of this test was to determine what preparation procedure, if any, is required
for the pit walls and floor prior to coating with polyurea. For this test, the paint quality
on the weathered concrete cover block best represents the paint quality within the pump
and valve pits. The testing was conducted in accordance with ASTMD 4541, Standard
Test Method f o r Chemical Resistance of Coatings Used in Light- Wuter Nuclear Power
Plants, as required by the project HNF-SD-W314-PDS-005 Rev. 3.
RF'P-7806 Rev. 0 4
Procedure
Four test coupons measuring 6"x6"x2" were cut from an unused, weathered, Amercoat
painted cover block. Each coupon had a different preparation procedure performed on it
before the polyurea coating was applied.
Procedure #I was washed with water and scrubbed lightly with a brush
Procedure #2 was washed with water only.
Procedure #3 was washed with a glycerin fixative.
Procedure #4 was not prepared at all.
Procedure #5 applied polyurea to bare concrete. The concrete backsides of the
coupons used for procedure #4 were used for this test.
After the preparations procedures were completed, the coupons were fully encapsulated
in a coating of approximately 60 mil (1/16") polyurea and allowed to fully cure.
The coupons were visually inspected, and subjected to pull-off testing using an
Elcometer, Model 106 Adhesion Tester following procedure ASTM D 4541-95, Standard
Test Method for Pull-off strength of Coatings Using Portable Adhesion Testers. As
directed by the ASTM procedure three pull-off tests were performed on each test coupon
to ensure accuracy of the testing process.
Results
Preparation procedure #1 (water wash with brush scrub) yielded only one pull-off where
there was no concrete attached to the polyurea.
Preparation procedure #2 (water wash only) also yielded only one pull-off where there
was no concrete attached to the polyurea. Overall, there was less concrete pulled off of
preparation group #2 than from preparation group #1, see pictures in appendix C.
Preparation procedure #3 (glycerin wash), yielded only one pull-off test where a
substantial amount of concrete was pulled up with the paint and polyurea. The remaining
pull-off tests resulted in a failure between the polyurea and the Amercoat paint.
Procedure #4 (no preparation) surprisingly yielded slightly better results than procedures
#I, and #2. The existing paint (Amercoat) on the concrete coupons was very weathered
(exposed to the elements for a minimum of 25 years). For this reason, it was
hypothesized that the results from preparation group #4 would be less desirable than
those from the other preparation procedure groups. On the contrary, second only to the
bare concrete group results, preparation group #4 yielded the most desirable results with
concrete failure resulting in all six pull-off tests.
RPP-7806 Rev. 0 5
Procedure #5 (bare concrete) yielded expected results. The test was performed on the cut
concrete side of preparation group #4. This concrete was hidden from the weathering
elements two inches deep within the cover block, and had not suffered any damage from
natural weathering or thermal cycling, as had the concrete in the other test groups. The
pull-off values for the bare concrete test range from 400 to 500 psi. These values were
expected, and follow accepted ranges for cured high quality concrete.
The data for each preparation group were averaged and the results compared to determine
which preparation procedure yielded the highest pull-off strength. See Appendix B.
With concrete failure evident in all adhesion testing except procedure #3 (the glycerin
fixative washed concrete), it is clear that preparation procedures #1, #2, and #4 are all
adequate surface preparations for the purpose of recoating used pump and valve pits. Of
the five preparation procedures, the glycerin wash (procedure #3) consistently yielded
undesirable results. The glycerin solution acted as a bond breaker between the polyurea
coating and the Amercoat paint, not allowing the polyurea to adhere to the underlying
substrate.
Conclusion
In surface preparation procedure #3 where the glycerin fixative used in the tank farms
was left on the sample coupons, the adhesion failure occurred between the Amercoat and
polyurea layers. To maintain proper adhesion to the substrate it was concluded that the
glycerin fixative should be removed from the pit walls and floors prior to the application
of polyurea.
The pull-off strength testing documented in this report shows that a pull-off strength
above 200 psi caused the failure to occur within the concrete, rather than between the
SPC coating and the concrete. It is therefore concluded that the minimum required
adhesion strength specified in the HNF-SD-W314-PDS-005 3, should be changed
Rev.
from the current value of 900 psi to a value of 200 psi for weathered or thermal cycled
concrete.
A higher adhesion strength criterion has been selected for new, not previously coated
concrete. The higher value is based on concrete compressive strengths of 3000 psi to
5000 psi for cast-in-place structural lightweight concretes (ASTM STP 169C, pg. 528 &
the example, below) and “the ratio of tension to compressive strength of concrete ranges
between 0.07 and 0.1 1” (ASTM STP 169C, pg. 133). The concrete tensile strength
applicable to new concrete applications is 350 psi, therefore the associated adhesion
strength requirement is assigned this same value.
Example: Construction Requirements for Hanford Tank Farms: Project W-
314 Construction SpecEficntion Genernl Requirements 200 Eust Waste
Transfer System W-314-C6. Project Specification 134 210 03300 Cast-iu-
Place Concrete section 2.2.1.4, Page #4 of 8. “Minimum allowable
compressive strength: 4000 psi at 28 days”.
RPP-7806 Rev. 0 6
This value was derived from a combination of nominal concrete compressive and tensile
strength values (3000 psi X 0.07 = 210 psi and 5000 psi X 0.1 1 = 550 psi) and
manufacturers data showing that polyurea adhesion strength of 550 psi can be achieved if
a concrete primer is applied (Specification Data Sheet for Envirolastic AR 425, February
2000).
RADIOLOGICAL EXPOSURE
The project’s evaluation of the radiation tolerance requirement contained in HNF-SD-
W3 14-PDS-005 Rev. 3, started in RPP-7187 Project W-314 Pit Couting Repuir
Requirements Analysis and continued with this testing, determined that the accumulated
radiation exposure (6.0 X 107R)over the expected lifespan ofthe ofthe coating (12
years), is excessive.
The project therefore, re-evaluated this requirement and selected 1.0 X IO7R as a more
appropriate and yet conservative total cumulative dose tolerance requirement. This
reduced radiological dose was then used for the following radiation tolerance testing.
Adhesion strength after exposure to gamma radiation has not been addressed by any of
the polyurea manufacturers. 1.0 X l0’R of Gamma radiation was chosen as a
representative maximum exposure value for the life of a coating inside a pump or valve
pit.
Samole Dose Calculations:
1. AZ pits dose rates are 3 rihr. To build up 1.0 X 107Rtotal dose, therefore,
requires 1.0 X 1O7R/((3r/hr)(24 hr/day)(365 day/yr)} = 380.5 years. This is the
expected lifespan of the coating at a dose rate of 3 r/hr. This calculation is
conservative for it does not take into account the % lives of the radioisotopes.
2. The lifespan of the coating is expected to be 12 years according to the
requirement in HNF-SD-W314-PDS-005 Rev. 3. The dose rate required to
achieve 1.0 X 107Rwithin a 12 year period is therefore, 1.0 X 1O7R/((24
hr/day)(365 day/yr)(l2 yrs)} = 95.1 dhr. A 95 rihr average dose rate greatly
exceeds the average dose rates expected in the pump and valve pits.
Based on the above discussion of the excessive conservatism in the current
6.0 X 107R HNF-SD-W314-PDS-005 Rev. 3 requirement, it is recommended that this
requirement be revised to 1 .0 X 107R. Before this modification is made, it should be
verified that pit dose rates are not expected to approach 95 rihr for any extended period of
time in any pump or valve pits.
There was no data on the Envirolastic AR 425 product that had been selected by the
project to show that it met the above requirement. The radiation tolerance testing was
therefore conducted to determine if any significant changes resulted from exposure to
1.0 X 107Rof Gamma radiation.
RPP-7806 Rev. 0 7
Procedure
Eight test coupons measuring 4"X 4"X 2" and four test coupons measuring 6"X 6"X 2"
were cut from an unused, weathered, Amercoat painted cover block, found in a waste
yard at 200-west area. These coupons were then separated into preparation procedure
groups, each containing two small blocks (irradiated) and one large block
(non-irradiated).
Preparation #1 was washed with water and scrubbed lightly with a brush.
Preparation #2 was washed with water only
Preparation #3 was washed with a glycerin fixative,
Preparation #4 was no preparation at all
Procedure #5 applied polyurea to bare concrete. The concrete backsides of the
coupons used for procedure #4 were used for this test.
After the preparations were completed, the coupons were fully encapsulated in a coating
of approximately 60 mil (1116") polyurea and allowed to fully cure. The coupons were
then delivered to the Gamma Irradiation Facility (Bldg. 3730) in the 300 area of Hanford
where they were exposed at a dose rate of 1.69 X 105FUhrfrom a "Cobalt source until
they had received a total cumulative dose of 1.0 X lO'R. After radiation exposure, the
coupons were visually examined for softening, blistering, delamination, color change,
and peeling. The examination disclosed only a slight change in color of the polyurea
samples from gray to a slightly darker olive tinted gray. No other changes were noted.
Envirolastic AR 425 is composed of aromatic compounds, and will he subject to a slight
color change when exposed to large quantities of ultra violet energy. It was therefore
hypothesized that a large quantity of a higher energy (gamma) may result in the same
type of color change.
In addition to the visual examination, these irradiated coupons underwent pull-off testing
to determine the polyurea adhesion strength utilizing an Elcometer, Model 106 Adhesion
Tester, following the procedure ASTM D 4541-95.
Three pull-off tests per coupon were performed on each of the irradiated samples
Results of the pull-off tests from the irradiated coupons were averaged and compared
with the pull-off test result averages from the non-irradiated coupon, to determine if
gamma radiation of 1.O X 1O had any adverse impact upon adhesion strength. See
'
R
appendix C.
RPP-7806 Rev. 0 8
Conclusion
After all test coupons were irradiated, they were visually inspected for defects in the
Polyurea coating such as color change, delamination, blistering, and softening. A color
change from gray to a slightly darker olive gray was the only change noted in the coating.
In preparation groups #1, #2, #4, and #5 the average pull-off strength of the non-
irradiated samples fell in between the average pull-off strength of the irradiated samples
(lot #1 and lot #2). In preparation group #3 (glycerin wash), the non-irradiated sample
had a slightly higher pull-off strength than that of the two irradiated samples. Based on
this data it is clear that 1.0 X 107Rgamma radiation does not affect the adhesion strength
of polyurea. See appendix C.
DECONTAMINATION FACTOR (DF) TESTING
Though decontamination factor (DF) data existed for one polyurea SPC formulation
indicating that it was close to meeting the project’s requirements, there was no DF data on
the Envirolastic AR 425 product that had been selected for this project.
Procedure
Four test coupons as described in the tank waste compatibility section, including two with
a slightly stippled finish and a paper backing were used for the DF testing. The testing
was performed by PNNL at Bldg. 325 in the 300 area of Hanford and followed the
procedure ASTM D 4256, Standard Test Methodfor Determination of the
Decontuminahility of Coatings Used in Light- Water Nuclear Power Plants with the
following exceptions:
Hanford tank waste from tank 241-AN-107 was used instead of the solution of
Cesium and Cobalt described in the ASTM standard. The tank waste was used as
a more realistic Hanford alternative to the standard solution.
Both procedure-testing parameters A & B were performed. However, the acid
decontamination information has not been used to draw conclusions. Use of acid
solutions for decontamination purposes in tank farm facilities is prohibited by
tank farm specifications.
It was found during the polyurea mock-up training at Hammer facility that a slight over
spray might be experienced while spraying the pits with polyurea. This over spray
creates a stippled finish rather than the desired smooth finish, and may affect the
decontamination factor. Therefore a set of coupons with a slightly stippled finish was
included in the DF testing. These coupons were subjected to Procedure A of ASTM D
4256 without the acid decontamination procedures, and are labeled test coupons “D”.
Test coupons “A” were subjected to procedure “A” testing of ASTM D 4256 without the
acid decontamination procedures.
RPP-7806 Rev. 0 9
Test coupons “B’ were subjected to procedure “B” testing of ASTM D 4256. This test
procedure was deemed unacceptable and not applicable to the tank farm environment.
See “Results”.
Test coupons “C” were a failed attempt at testing the stippled finish with paper backing
coupons. During the wash process some of the contamination was trapped in the paper
backing on the coupon. It was decided a jig had to be manufactured in order to protect
the paper backing on the coupon from contamination during the water wash stage of the
testing. See appendix D
Test coupons “D” were subjected to procedure “A” testing of ASTM D 4256 without the
acid decontamination procedures.
Results
During the testing it was noted that the gamma contamination does not stick to the
polyurea well unless it has been dried on as described in procedure “A” of ASTM D
4256. In procedure B the contaminant solution was not allowed to dry; therefore, the
initial contamination values were substantially smaller than that of procedure “A”.
When the coupons were decontaminated, procedure “B” had less contamination to
remove resulting in much lower DF values that that of procedure “A”. It has been
decided that the more realistic DF values for a pump or valve pit application come from
procedure “A” and therefore, procedure “B” values will not be used.
The Decontamination Factor (DF) requirement for an in-pit SPC is 20 (95%) with just a
water wash, and 100 (99%) after washing with a decontamination solution.
The results from Part A testing of a smooth finish (test coupons “A”) indicate that the
isotope 137Cs be decontaminated to a DF value of between 202 (99.50%) and 274
can
(99.63%). Results indicate that the 137Csisotope is the most difficult to remove when
compared with “Co, ‘54Eu,I5’Eu and 24’Am.The DF values for ‘OCo are 1553-1663
E~
(99.94%), ‘ 5 4are 2696-2892 (99.96%), 1 5 5 E ~ 1618-1736 (99.94%), and for 241Am
are
is 3556-3621 (99.97%). See appendix D.
The results from Part A testing of a stippled over spray finish (test coupons “D”) indicate
that the isotope 137Cs be decontaminated to a DF value of between 135 (99.26%) and
can
211 (99.53%). The DF values for 6oCoare 1550-1727 (99.94%), Is4Eu are 2623-2800
(99.96%), ‘55Euare 1620.1672 (99.94%), and the values for 24’Amare 3070-3127
(99.97%).
Conclusion
It is clear that Envirolastic AR 425 greatly exceeds the decontamination factor (DF)
required by “F-SD-W3 14-PDS-005.
RPP-7806 Rev. 0 10
GENERAL CONCLUSION
Two project Special Protective Coating requirements will be revisited based on the
results of these tests. First, the adhesion strength requirement of 900 psi was determined
to be an adhesion strength when an SPC coating is applied to steel and was not an
appropriate adhesion strength requirement for a coating when applied to concrete. Using
the test results from this report as well as industry standards the adhesion strength
requirements are being changed to 200 psi for old weathered or thermal cycled concrete,
and 350 psi for new fully cured and primered concrete. These changes to HNF-SD-
W314-PDS-005 Rev. 3 are included in ECN 665749 and ECN 667133.
Second, the resistance to radiation requirement of 6.0 X 1O’R was determined to be
excessively high. The level chosen for this requirement is still very conservative for the
upcoming application of polyurea in the AZ Tank Farm Pits. Pump and valve pits being
refurbished by Project W-3 14 will be evaluated for their respective radiation levels before
generating the radiation criteria revision to HNF-SD-W314-PDS-005 Rev. 3. It is
however, concluded that the total radiation dose criteria of 1.O X 107Ris adequate for use
in the AZ Farm 01A and 02A pits. It is also anticipated that this value will be adequate
for all project W-314 pits, but verification of pit dose levels will precede finalizing this
determination.
Envirolastic AR 425 is adequate for use in the Tank Farms as a secondary containment
coating in pump and valve pits. It meets or exceeds all the requirements contained in the
requirement document HNF-SD-W314-PDS-005 Rev. 3. Surface preparation calls for
the removal of any glycerin fixative from the walls and floor before the application of the
polyurea coating to prevent an undesirable adhesion strength. With regard to
decontamination factor, there is no need to worry about a slightly stippled finish from
over spray during application; however, it is still preferred that the surface of the
polyurea coating be as smooth as reasonably achievable.
RPP-7806 Rev. 0 11
APPENDIX A
POLYUREA COMPATIBILITY
WITH
TANK WASTE
RESULTS
SPREADSHEET
&
WASTE
CHARACTERIZATION
RPP-7806 Rev. 0 1-A
8:05 AM
No blisters
No color change
No delaminating
Scratch test is Scratch test is Scratch test is Scratch test is
negative with no
softening of the
1/30/01
8:05 AM
No blisters
No color change No color change
No delaminating
Scratch test is Scratch test is Scratch test is Scratch test is
negative with no
softening of the
RPP-7806 REV. 0 2-A
113 1/01
10:20 AM
No blisters No blisters No blisters
No color change No color change No color change
No delaminating No delaminating No delaminating
Scratch test is Scratch test is Scratch test is
negative with no negative with no negative with no
softening of the softening of the softening of the
01 urea
PY 2/1/01
2:20 PM
No blisters
No color change
No delaminating
Scratch test is Scratch test is Scratch test is
negative with no
softening of the
2/2/01
2:35 PM
No blisters
No color change No color change
No delaminating No delaminating - No delaminating
Scratch test is Scratch test is Scratch test is
negative with no
softening of the
RPP-7806 REV. 0 3-A
Data Dictionary to Reports in this Document
.Report. . . . . . . . . . . . . . . .
. . . . . . . . . . .Field . . . . . . .
..... .... Description
................................
...... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Best Basis Inventory Estimate for Contains best basis constituent inventory
Nonradioactive Components estimates for non-radioactive contents of the
Hanford waste tanks.
Analyte The name of the constituent used for reporting
purposes.
Total Inventory Best Basis Inventory estimate, reported in kg.
Basis The basis for the inventory value.
Comment Further information to clarify the information in
the table.
.................................................................
Best Basis Inventory Estimate for Contains best basis constituent inventory
Radioactive Components estimates for radioactive contents of the Hanford
waste tanks.
Analyte The name of the constituent used for reporting
purposes.
Total Inventory Best Basis Inventory estimate, reported in Ci.
Basis The basis for the inventory value.
Comment Further information to clarify the information in
the table.
..................................................................
Best Basis Inventory Calculation Detail This report contains the detailed calculations
showing the actual concentration, density,
volume, and unit adjustment values used to
derive inventory values by analyte by phase.
Analyte Standard best-basis analyte expressed as
chemical symbol (reported without charge
designation per the hest-basis inventory
convention). --
Waste PhaseIType Waste Phase is the phase of waste to which the
concentration data is applicable (e.g.,
supernatant, saltcake, sludge, liquid, solid, etc.).
The Waste Type is the waste type as defined in
HDW Rev. 4 or as defined by "templates" (e.g.,
SMMA1, SMMT1, etc.).
Inventory Tank inventory value reported in standard units
(kg or Ci).
Basis Indicates the basis for the best-basis inventory
concentration data. (S - Sample-based, M -
Model-based, C - Calculated, E - Engineering
assessment-based, X - Waste transfer)
RI'I'-7ROh Rev. 0 1 4-A
Data Dictionary to Reports in this Document
Report Field Description
Formula The mathematical expression for the calculation
used in deriving inventories.
Calculation Detailed calculation showing the actual
concentration, density, volume, and unit
adjustment values used to derive the
corresponding inventory value.
IWP-7806 Rev. 0 2 5 -A
Best-Basis Inventory Estimate for Radioactive Components in Tank 241-AP-101
'H 2.90E+01 S
14C l.llE+OO S
59Ni 1.13E+00 E
V O 3.18E+01 S
6'Ni 1.12E +02 E
79Se 2.45E-01 S
%r 4.28E +02 S
I I 4.28E+02 I C Based on 90Sr
i 93Zr I 2.57E+01 I E
%Tc 1.99E +02 S
IwRu 1.38E3-02 E
1Z5Sb I 1.22E+03 I SIE
126Sn I 3.57E+OO I SIE
I , 1291 I 3.39E-01 I S
134cs 1 1.66E+03 I S
137rnga I 6.64E+05 I C Based on 137Cs
152E~ 1.16E+01 SIE
lS4Eu 1.40E +01 SIE
'"Eu 1.31E+01 E
lZ6Ra 2.10E-04 E
lZ7Ac 1.23E-03 E
'18Ra 4.60E-01 E
'19Th 1.07E-02 E
231Pa 5.75E-03 E
232Th 5.60E-02 E
2 y J
6.64E-02 E Calculated using the Pu and U
distribution spreadsheet.
-
111'1'-7806 Rev. 0 S 6-A
Best-Basis Inventory Estimate for Radioactive Components in Tank 241-AP-101
Decayed to January 1, 1994 (Effective January 1, 2001)
lated using the Pu and U
distribution spreadsheet.
Calculated using the Pu and U
ulated using the Pu and U
ibution spreadsheet.
'S=Sample concentration from the tank of interest
M =Hanford Defined Waste (HDW) model concentration data
E=Derived from engineering assessment or process knowledge
including application of sample data from other tanks of interest
C=Calculated from other analyte data (e g., '"Y from ?3', '""'Ba from
'37Cs,U isotopes from ON from charge balance, alpha isotopes
from total alpha, etc.)
1ll'P-7806 llcv 0 6 7-A
m
TT T T TT T- T T
lU'l'-7XO6 Rcv. 0 9-A
TT T1T TT
T
1<1'1'-7806 Rev. 0 IO-A
l- T
T 7-
T
T
I I-A
RI'V7806 Jicv. 0 12-A
rr T I
13-A
Best-Basis Inventory Estimate for Radioactive Components in Tank 241-BY-106
8 S5E-01 Based on UTOTAL and HDW model
isotopic distribution; saltcake layei
~
~ ~~~
J<l’l’-7XO6 Jlcv 0 5 14-A
Best-Basis Inventory Estimate for Radioactive Components in Tank 241-BY-106
DI ed to January 1, 1994 (EffectiveJanuary 31, 1997)
Corn
)
M,E, or C ’
2 3 3 ~
3.28E+OO 1 C Based on UTOTAL and HDW model
isotopic distribution; saltcake layer
only
I
2 3 4 ~
C Based on UTOTAL and HDW model
2.33E-01 isotopic distribution; saltcake layer
2 3 5 ~
8.63E-03 1 C
OdY
Based on UTOTAL and HDW model
isotopic distribution; saltcake layer
only
236”
7.73E-03 C Based on UTOTAL and HDW model
isotopic distribution; saltcake layer
only
Z37Np 1.31E+00 M
238pu
+
2 .OOE 00 C Based on 239Pu and HDW model
isotopic distribution in the sludge;
based on Total Alpha and HDW
model isotopic distribution in the
BYSltCk
2 3 8 ~
1.94E-01 C Based on UTOTAL and HDW model
isotopic distribution; saltcake layer
only
239h
7.19E+01 C Based on 239/240Pu and HDW model
isotopic distribution in the sludge;
based on Total Alpha and HDW
model isotopic distribution in the
BYSltCk
Based on 239/240Pu and HDW model
isotopic distribution in the sludge;
c
based on Total Alpha and HDW
model isotopic distribution in the
BYSltCk
24’Am 5.38E+01 Based on total alpha and HDW model
isotopic distribution
24’Pu 1.44E+02 Based on 239Pu and HDW model
isotopic distribution in the sludge;
based on Total Alpha and HDW
model isotopic distribution in the
BYSltCk .
~~. _ ___~ ~
15-A
Best-Basis Inventors Estimate for Radioactive Components in Tank 241-BY-106
Decayed io January 1, 1994 (EffectiveJanuary 31, 1997)
Analyte Comment
Total Inventory (Ci)
Basis
(S,M,E, or C)'
242Cm 3.05E-03 C Based on total alpha and HDW model
isotopic distribution
2"pu 6.93E-04 C Based on 239Pu and HDW model
isotopic distribution in the sludge;
based on Total Alpha and HDW
model isotopic distribution in the
BYSltCk
2 4 3 b
1.86E3-03 C Based on total alpha and HDW model
- isotopic distribution
243Cm 6.23E-05 C Based on total alpha and HDW model
isotopic distribution
''Ym 2.73E-04 C Based on total alpha and HDW model
isotopic distribution
KPP-7806 Rev. 0 7 16-A
R1'1'-7806 Rev. 0 1I - A
18-A
Rl'l'-7806 Jlcv. 0 19-A
20-A
R1'1'-7806 Rcv. 0 21-A
U U U U
~
.- is i3
U
8
i3
3
9 + 4
4 2 !-2
'?
i-2 2 p
m
!
N
v!
m
x
u
v)
5
4
-
U
c
m
v)
22-A
.-
E
t U U U
is i3
is 3
8 0
+
I
z
ri
c
0
I 1
111'1'-7806 Rev. 0 23-A
*
J
4
.
l<l'P-7806 RCV. 0 24-A
25-A
APPENDIX B
POLYUREA
ADHESION STRENGTH
RESULTS
SPREADSHEET
&
PICTURES
RPP-7806 Rev. 0 1-B
Adhesion StrenEth ( P u l l - m
-
Lot #1 Test 175 I 250 I 400 I
Irradiated #I No A little A little
Polyurea concrete concrete and concrete
Coated and very paint pulled pulled off
Amereoat little paint off
Painted ~
pulled off
Concrete Test I15 I 300 I 500 I
#2 No Lots of A little
concrete concrete and concrete
and very paint pulled pulled off
little paint off
~
p l l e d off
Test 200 I 300 I 500 I
#3 Lots of Lots of A little
concrete concrete and concrete
paint pulled pulled off
pullc.J of< pullctl otf
" - 233 216 - -
Lot #2 350 I 400 I
I rrddi ated #I Lots of Lots of No Lots of A little
Polyurea concrete concrete and concrete
Coated no paint paint pulled pulled off
Amercoat ~
p l l e d off off
Painted Test 200 I 300 I 450 I
Concrete #2 Very little Lots of A little
concrete concrete and concrete
and paint paint pulled pulled off
~
Test
#3
z75 p" I g l j d
Lots of
off
Lots of
p l l e d off
200 I
Very little
215 I
0 ff
Lots of
500 I
A little
concrete and concrete concrete concrete and concrete
naint Dulled and mint and paint paint pulled pulled off
off
~
.
RPP-7806 Rev. 0 2-B
+-
Lot #3
Jnirradiated #I Lots of A little No A little A little
Polyurea concrete concretc concrete
Coated and paint and paint and paint
Amercoat 1 pulled off 1pulled off^ pulled off
Painted Test 12501 12501 225 I
Concrete Lots of Lots of A little Lots of A little
concrete concrete and concrete and concrete
and paint and paint concrete paint pulled pulled off
pulled off pulled off and paint off
pulled off
Test 5 0 1 of
Lots
2 concrctc concrete 250 I
Lots of Lots of A little
concrete
and a little and a little and paint
Avemge Rr
oaint mint pulled off
Off I
I
267 '467
RPP-7806 Rev. 0 3-B
‘iest L A
Individui
puI I-off
f’REPAKA‘llON GIIOUI’ # I
WA‘I’ER W A S l l WITH BIIIJSH SCKIJB
LARGE BILX’K IS ‘I’HE NON-IKKADIA’I‘ED CON’I’ROL
2 SMALLER BLOCKS HAVE BEEN I R R A D I A T E D 1.0 x 1 0 ’ ~
‘1‘0
RPP-7XO6 Rev. 0
i Tcst Lor #3 I
Individual
pul 1-011'
i
PREF'ARA'I'ION GKOIIP #2
WATER WASH O N L Y
LAKCiE B L O C K IS THE NON-IliKADIA'IED C O N ' I K O L
2 S M A L L E R B L O C K S H A V E B E k N I R R A D I A T E D '1'0 1.0 X IO'R
RPP-7800 Iicv. 0 5-B
i Individual
pull-oft
tests
PKI3'AKATION GR.OIJP #3
W A T E K W A S H WITH GLYC'EKIN FIXA7'1VE
S
1,AKCiE B L O C K I 'I'HE NON-lKKADlA1'ED CON'I'KOL
2 S M A L L E R B L O C K S H A V E BEEN IKKADIA'I~EDTO 1.1 X 10'11
RPP-7806 Rcv. 0 6-B
pull-off tests
-I Test Lot#? 1
PREPARATION G R O U P #4
N O I’REPAKA‘I ION
L A R G E B L O C K IS T H E NC)N-IRRADIATED C O N T R O L
2 S M A L L E R B L O C K S H A V E BEEN IKKADIATED TO 1. I X 10’R
RPP-7806 Rcv. 0 7-H
PREPARA‘I’ION GKOIJI’ #S
B A K E CONC’RRl’t: - N O PREPAKATION
L A K G E BLOCK IS 7 HE NON-IRRAI)IATED CON‘T’KOL
2 S M A L L E R BLOCKS H A V E BEEN I R R A D I A T E I I TO I . 1 X IO’R
RPP-7800 Rcv. 0
APPENDIX C
POLYUREA
RADIOLOGICAL
EXPOSURE
RESULTS
SPREADSHEET
&
PICTURES
RPP-7806 Rev. 0
.
..
ICOVK I
BLOCK
COIJPON
LOTS
Rf’P-7806 Rcv. 0 2-c
Color Comparison of polyurea
RPP-7806Rev. 0 3-c
APPENDIX D
POLYUREA
DECONTAMINATION
FACTOR (DF)
RESULTS
SPREADSHEETS
&
PICTURES
RF'P-7806 Rev.0 1-D
Decontamination Factor (DF) Testing
Project 42161
R Mauser
212 1101
Decontamination of Coatings by Procedure ASTM D 4256, and RPP-7531
Four coupons with polyurea coatings were received from R. Mauser for decontamination testing
according to ASTM procedure in RPP-7531. By agreement with the client, Hanford tank waste
from tank AN107 was used for the testing in place of standards. The coupons were exposed to
the tank waste as per part A and B of the procedure, then decontaminated in water and the
prescribed acid solution. Gamma counting was performed following each treatment. The listed
I-sigma uncertainties only refer to the relative counting results. Absolute values have a higher
uncertainty due to the non-standard geometry of the specimens. Results show that the water
decontamination as per part A of the procedure has a DF value of 1500-3600 for most isotopes;
however, Cs-I37 is only reduced by a factor of about 250.
I
Part A Testing - Water Decon
Activities are listed in microcuries per sample
CO-60 1.483-2 < 8.93-6 > 1663 1.463-2 < 9.43-6 > 1553
+I- 3% +I- 3%
CS-137 6.073-3 3.003-5 202 5.863-3 2.143-5 274
+I- 6% +I- 15% +I- 7% +l-20%
311-154 6.943-2 < 2.43-5 > 2892 6.803-2 < 2SE-5 > 2698
+I- 2% +I- 2%
311-155 4.533-2 < 2.83-5 > 1618 4.743-2 < 2.13-5 > 1736
+I- 4% +I- 4%
Am-241 8.893-2 < 2.53-5 > 3556 8.693-2 < 2.43-5 > 3621
+I- 5% +I- 5%
RPP-7806 Rev. 0 2-D
EATTEtLE / PACIFIC NORTHWEST NATIONAL LAB 23-JAN-2001 15:57:17.00
RADIOCHEMICAL PROCESSING LABORATORY (325 BLDG.) ’ GAMMA ENERGY ANALYSIS
RADIOANALYTICAL APPLICATIONS TEAM (GEA)
%--&
2%@,
Sample Title: A1 23/4inch L by 2inch H lead w/ spot / Mauser y / 4
Config. File: DKA200: [TJSER.SCUSR.ARCHIVEISMP G3751.CNF;l
Analyd. File: ND-SC-ASF:COMMON.ASF
-
&
{ b3l,Ol
Effie, File : DKA2OO:tUSER.SCUSR.EFFlEFF -G3GSVZMLW-RT
Library File: nd-sc-1ib:common.nlb
Backgnd File: BKG-G3GSVlOMLW.CNF;38 - 5-JAN-2001 11:39:05.
Acquisition time : 23-JAN-2001 15:28:52 Sample quantity: 1.00000E+00 sample
Sample (EOI) time: 23-JAN-2001 15:28:52 Sample geometry: P3-GSV-2ML-W
Elapsed live time: 0 00:15:00.00
Elapsed real time: 0 00:15:12.69 1.4%
Peak Search Sens.: 5.00000
Eng. Tol. (FWHM) : 0.75 Half life ratio: 8.00
Errors propagated: Yes Systematic Erro: 1.30
Abundance limit : 70.00 WTM error limit: 3.00
Analyses by : PEAK V16.6 PEAKEFF V2.2 ENBACK V1.5 NID V3.2
WTMEAN V1.8 MINACT V2.5
Nuclide Line Activity Report -
Nuclide Type: Activation’
Uncorrected Decay Corr 1-Sigma
Nuclide Energy %Abn %Ef€ uCi/sample uCi/sample %Error Status
CO-60 1173.24 99.97 3.5343-01 1.4593-02 1.4593-02 3.14 OK
1332.50 99.99* 3.1993-01 1.4983-02 1.4983-02 2.84 OK
2505.74 -- Miscellaneous-- - - - - - Line Not Found - - - - - Absent
Final Mean for 2 Valid Peaks = 1.4803-02.1.1-3.117E-04 ( 2.11%)
Nuclide Type: Fission
Uncorrected Decay Corr 1-Sigma
Nuclide Energy %Abn %Eff uCi/sample uCi/sample %Error Status
CS-137 661.66 85.20* 5.4843-01 6.0663-03 6.0663-03 5.52 OK
Final Mean €or 1 Valid Peaks = 6.0663-03+/- 3.3483-04 ( 5.52%)
EU-154 123.07 40.60 1.7233+00 7.0313-02 7.0313-02 2.19 OK
247.93 6.91 1.2263+00 6.4643-02 6.4643-02 6.04 OK
591.76 4.96 5.9923-01 7.1883-02 7.1883-02 7.74 OK
692.42 1.79 5.2873-01 8.801E-02 8.8013-02 17.86 OK
723.30 20.11 5.114E-01 6.8393-02 6.8393-02 3.67 OK
756.80 4.54 4.938E-01 7.1023-02 7.1023-02 7.70 OK
RPP-7806 Rev. 0 3-D
Wiclide Line Activity Report (continued) Page : 2
Sample ID : A1 Acquisition dace : 23-JAN-2001 15:28:52
Nuclide Type: Fission
Uncorrected Decay Corr 1-Sigma
Nuclide Energy %Abn %Eff uCi/sample uCi/sample %Error Status
873.19 12.20 4.4263-01 7.3163-02 7.3163-02 4.34 OK
996.26 10.53 4.0043-01 6.8843-02 6.8843-02 5.79 OK
1004.25 17.91 3.9783-01 7.0833-02 7.0833-02 3.68 OK
1274.44 35.00* 3.3133-01 6.6953-02 6.6953-02 2.60 OK
1596.49 1.79 2.7583-01 7.5813-02 7.5813-02 9.49 OK
Final Mean for 11 Valid Peaks = 6.9393-02+/- 8.5313-04 ( 1.23%)
EU-155 60.01 1.13 8.961E-01 2.8253+00 2.8253+00 6.15 <<WM Interf
86.54 30.85 1.5293+00 4.5923-02 4.5923-02 4.90 OK
105.31 21.20* 1.6933+00 4.4593-02 4.4593-02 5.20 OK
Final Mean for 2 Valid Peaks = 4.5273-02+/- 1.6143-03 ( 3.57%)
Nuclide Type: fission
Uncorrccted Decay Coir 1-Sigma
Nuclide Energy %Abn %Eff uCi/sample uCi/sample %Error Status
AM-241 59.54 35.90* 8.9613-01 8.8933-02 8.8933-02 4.59 OK
Final Mean for 1 Valid Peaks = 8.8933-02+/- 4.0793-03 ( 4.59%)
RPP-7806 Rev. 0 4-D
Post-NID Peak Search Report Page : 3
Sample ID : A1 Acquisition dace : 23-JAN-2001 15:28:52
It Energy Area FWHM Channel Left Pw %Err Fit Nuclides Activity
uCi/sample
6 42.07 565 1.00 102.65 98 13 25.6 5.433- 01
6 43.08 1257 1.19 105.34 98 13 13.8
0 48.83 666 0.92 120.80 116 11 30.0
0 59.48 9527 1.10 149.40 141 15 3.1 AM-241 8.8933-02
EU-155 2.83
0 86.62 7215 1.09 222.25 217 11 3.3 EU-155 4.5923-02
0 105.37 5330 1.13 272.58 267 12 4.3 EU-155 4.4593-02
0 123 .ll 16377 1.14 320.22 314 13 1.5 EU-154 7.0313-02
0 248.05 1823 1.24 655.69 650 13 5.9 EU-154 6.4643-02
0 582.59* 14 0 1.53 1554.21 1543 20 39.5
0 591.73 711 1.57 1578.75 1569 18 7.6 EU-154 7.1883-02
0 661.59 944 1.91 1766.43 1758 16 5.4 '3-137 6.0663-03
0 693 .ll 278 2.15 1851.12 1841 21 17.8 EU-154 8.8013-02
0 723.41 2342 1.99 1932.53 1921 25 3.3 EU-154 6.8393-02
0 756.90 530 2.11 2022.51 2014 16 7.5 EU-154 7.1023-02
0 873.20 1316 2.06 2335.02 2322 25 4.1 EU-154 7.3163-02
0 903.52 145 1.97 2416.48 2405 20 23.5
0 996.37 966 2.33 2666.01 2652 26 5.6 EU-154 6.8843-02
0 1004.85 lGDl 2.38 2688.81 2677 25 3.4 EU-154 7.053E-02
0 1173.34 1716 2.96 3141.70 3128 27 2.9 CO-60 1.4593-02
0 1247.21 45 0.84 3340.28 3326 21 37.6
0 1274.46 2586 2.84 3413.56 3400 27 2.1 EU-154 6.6953-02
0 1332.51 1595 2.95 3569.62 3556 27 2.5 CO-60 1.4983-02
0 1408.00 37 2.16 3772.59 3761 20 19.2
0 1596.30 125 2.13 4278.98 4265 24 9.4 EU-154 7.5813-02
Minimum Detectable Activi'ty Report
Bckgnd Energy MDA
Nuclide SUm (keW (uci/sample 1
BE-7 668. 477.61 4.86653-03
IC-40 16. 1460.83 1.76243-03
MN-54 279. 834.84 5.09103-04
CO-58 331. 810.78 5.45203-04
FE-59 217. 1099.25 9.84383-04
SR-85 651. 514.00 5.52653-04
NB-94 1461. 871.09 1.20373-03
NB-95 357. 765.81 5.39883-04
RU-103 563. 497.05 5.41073-04
RURH-10 6 409. 621.92 5.00713-03
AG-10 8 M 2724. 722.90 1.56023-03
SB-125 748. 427.88 1.66053-03
SNSB-126 480. 666.30 5.63283-04
CS-134 332. 795.86 6.26303-04
CE-139 4335. 165.85 7.25123-04
CE-141 5473. 145.44 1.28243-03
CEPR-144 6151. 133.54 5.78543-03
EU-152 42. 1408.01 1.40803-03
HG-203 10109. 72.87 1.74863-02
RA-226P 983. 351.93 1.26323-03
RPP-7806 Rev. 0 5-D
Minimum Detectable Activity Report (continued) Page : 4
Sample ID : A1 Acquisition date : 23-JAN-2001 15:28:52
Bckgnd Energy MDA
Nuclide Sum (keW (uCi/sample)
TH-232P 2208. 238.63 1.20083-03
U-235s 3523. 185.71 9.69343-04
U-238s 1310. 1001.03 1.51363-01
RF'P-7806 Rev. 0 6-D
_- - .-
L
BATTELLE / PACIFIC NORTHWEST NATIONAL LAB 31-JAN-2001 08:16:49.45
RADIOCHEMICAL PROCESSING LABORATORY (325 BLDG.) ’ GAMMA ENERGY ANALYSIS
RADIOANALYTICAL APPLICATIONS TEAM (GEA)
V&r,
Sample Title: A1 piece of lead w/spot decon / Mauser F21838
Config. File: DKA200: [USER.SCUSR.ARCHIVE]SMP-G3777.CNF;l
Analys. File: ND-SC-ASF:COMMON.ASF
Effie. File : DKAZOO:[USER.SCUSR.EFFlEFF -G3GSV2MLW-RT
Library File: nd-sc-1ib:common.nlb
Backgnd File: BKG-03GSVlOMLW.CNF;38 - 5-JAN-2001 11:39:05.
Acquisition time : 30-JAN-2001 13:53:29 Sample quantity: 1.00000E+00 samp
Sample (EOI) time: 30-JAN-2001 13:53:29 Sample geometry: P3-GSV-2ML-W
Elapsed live time: 0 14:OO:OO.OO
Elapsed real time: 0 14:00:06.60 0.0%
Peak Search Sens.: 5.00000
Eng. Tol. (FWHM) : 0.75 Half life ratio: 8.00
Errors propagated: Yes Systematic Erro: 1.30
Abundance limit : 70.00 WTM error limit: 3.00
Analyses by : PEAK V16.6 PEAKEFF V2.2 ENBACK V1.5 NID V3.2
WTMEAN V1.8 MINACT V2.5
Nuclide Line Activity Report ’
Nuclide Type: Fission
Uncorrected Decay Corr 1-Sigma
Nuclide Energy %Abn %Ef f uCi/samp uCi/samp %Error Status
CS-137 661.66 85.201 5.4853-01 2.9953-05 2.9953-05 14.50 OK
Final Mean for 1 Valid Peaks = 2.995E-O5+/- 4.3443-06 ( 14.50%)
Flag: ‘‘*‘I = Keyline
RPP-7806 Rev. 0 7-D
. ~ -.. .
. . . . .
.- ..-_
_I. .. .~.
. . !
Post-NID Peak Search Report Page : 2
Sample ID : A1 piece of le Acquisition daie : 30-JAN-2001 13:53:29
It Energy Area FWHM Channel Left Pw %Err Fit Nuclides Activity
uCi / samp
0 661.39 261 1.62 1766.09 1757 17 14.4 CS-137 2.9953-05
Minimum Detectable Activity Report
Bckgnd Energy MDA
Nuclide SUm (keW (uCi/sarnp)
BE-7 525. 477.61 7.73723-05
IC-40 327. 1460.83 1.42203-04
m-54 215, 834.84 7.99543-06
CO-58 199. 810.78 7.56513-06
FE-59 149. 1099.25 1.46163-05
CO-60 130. 1332.50 8.89843-06
SR-85 1012. 514.00 1.23413-05
NB-94 199. 871.09 7.92923-06
NB-95 223. 765.81 7.66543-06
RU-103 495. 497.05 9.10623-06
RURH-10 6 307. 621.92 7.74323-05
AG-108M 2s4. '722.90 8.S093E-06
SB-125 584. 427.88 2.62053-05
SNSB-126 251. 666.30 7.26673-06
CS-134 215. 795.86 9.00533-06
CE-139 1696. 165.85 8.11163-06
CE-141 1718. 145.44 1.29083-05
CEPR-144 1657. 133.54 5.36593-05
EU-152 95. '.. 1408.01 3.77633-05
EU-154 125. 1274.44 2.39933-05
EU-155 1646. 105.31 2.8192E-05
HG-203 1465. 72.87 1.19373-04
RA-226P 888. 351.93 2.14373-05
TH-232 P 1520. 238.63 1.77913-05
U-235s 1931. 185.71 1.28163-05
U-238s 188. 1001.03 1.02503-03
AM-241 1027. 59.54 2.47983-05
RF'P-7806 Rev. 0 8-D
BATTELLE / PACIFIC NORTHWEST NATIONAL LAB 23-JAN-2001 16:15:35.75
RADIOCHEMICAL PROCESSING LABORATORY (325 BLDG.) ’ GAMMA ENERGY ANALYSIS
RADIOANALYTICAL APPLICATIONS TEAM (GEA)
Sample Title: A2 23/4inch L by 2inch H lead w/ spot / Mauser F21838
1
Config. File: DKA200: [USER.SCUSR.ARCHIVElSMP-G3752.CNF;l
Analys. File: ND-SC-ASF:COMMON.ASF
/ 31.c
Effic. File : DKA2OO:[USER.SCUSR.EFFIEFF -G3GSV2MLW-RT
Library File: nd-sc-lib:comon.nlb
Backgnd File: BKG-G3GSVlOMLW.CNF;38 - 5-JAN-2001 11:39:05.
Acquisition time : 23-JAN-2001 15:55:36 Sample quantity: 1.00000E+00 sample
Sample (EOI) time: 23-JAN-2001 15:55:36 Sample geometry: P3-GSV-ZML-W
Elapsed live time: 0 00:15:00.00
Elapsed real time: 0 00:15:12.86 1.4%
Peak Search Sens.: 5.00000
Eng. Tol. (FWHM) : 0.75 Half life ratio: 8.00
Errors propagated: Yes Systematic Erro: 1.30
Abundance limit : 70.00 WTM error limit: 3.00
Analyses by PEAK V16.6 PEAKEFF V2.2 ENBACK V1.5 NID V3.2
WTMEAN V1.8 MINACT V2.5
..
Nuclide Line Activity Report
Nuclide Type: Activation
Uncorrected Decay Corr 1-Sigma
Nuclide Energy %Abn %Eff uCi/sample uCi/sample %Error Status
CO-60 1173.24 99.97 3.5343-01 1.465E-02 1.4653-02 3.19 OK
1332.50 99.99* 3.1993-01 1.4573-02 1.457E-02 2.91 OK
2505.74 - - Miscellaneous-- - - - - - Line Not Found ----- Absent
Final Mean for 2 Valid Peaks = 1.4603-02+/- 3.1403-04 ( 2.15%)
Nuclide Type: Fission
Uncorrected Decay Corr 1-Sigma
Nuclide Energy %Abn %Eff uCi/sample uCi/sample %Error Status
CS-137 661.66 85.20* 5.483E-01 5.8613-03 5.8613-03 6.82 OK
Final Mean for 1 Valid Peaks = 5.8613-03+/- 3.998E-04 ( 6.82%)
EU-154 123.07 40.60 1.7233+00 7.1573-02 7.1573-02 2.33 OK
247.93 6.91 1.226E+OO 5.9333-02 5.9333-02 7.00 OK
591.76 4.96 5.9913-01 6.66l.E-02 6.661E-02 9.52 OK
692.42 1.79 5.2923-01 1.047E-01 1.047E-01 14.23 OK
723.30 20.11 5.114E-01 7.000E-02 7.000E-02 3.15 OK
756.80 4.54 4.9393-01 7.3103-02 7.3103-02 9.11 OK
RPP-7806 Rev. 0 9-D
Nuclide Line Activity Report (continued) Page : 2
Sample ID : A2 23/4inch L by Acquisition date : 23-JAN-2001 15:55:36
Nuclide Type: Fission
Uncorrected Decay Corr 1-Sigma
Nuclide Energy %an %Eff uCi/sample uCi/sample % E r r o r Status
873.19 12.20 4.4263-01 6.5813-02 6.5813-02 4.60 OK
996.26 10.53 4.004E-01 6.9023-02 6.9023-02 5.40 OK
1004.25 17.91 3.9793-01 6.7453-02 6.7453-02 3.86 OK
1274.44 35.00* 3.3133-01 6.4613-02 6.4613-02 2.65 OK
1596.49 1.79 2.7573-01 4.3433-02 4.3433-02 14.16 <cWM N-Sigma
Final Mean for 10 Valid Peaks = 6.8033-02+/- 8.6233-04 ( 1.27%)
EU-155 60.01 1.13 8.9803-91 2.7623+00 2.7623+00 6.04 <<WM Interf
86.54 30.85 1.5293+00 4.9943-02 4.9943-02 5.01 OK
105.31 21.20* 1.6933+00 4.5443-02 4.5443-02 4.90 OK
Final Mean for 2 Valid Peaks = 4.7433-02+/- 1.6643-03 ( 3.51%)
Nuclide Type: fission
Uncorrected Decay Corr 1-Sigma
Nuclide Energy %Abn %Eff uCi/sample uCi/sample %Error Status
AM-241 59.54 35.90* 8.9803-01 8.6943-02 8.6943-02 4.44 OK
Final Mean for 1 Valid Peaks = 8.6943-02+/- 3.8583-03 ( 4.44%)
Flag: "*I' = Keyline
RPP-7806 Rev. 0 10-D
Post-NID Peak Search Report Page : 3
Sample ID : A2 23/4inch L by Acquisition dage : 23-JAN-2001 15:55:36
It Energy Area FWHM Channel Left Pw %Err Fit Nuclides Activity
uCi/sample
0 42.83 1545 1.41 104.68 100 10 11.4
0 49.36 1038 2.59 122.21 116 13 22.4
0 59.54 9333 1.11 149.55 143 13 2.8 AM-241 8.6943-02
EU-155 2.76
0 86.60 7846 1.14 222.20 216 13 3.5 EU-155 4.9943-02
0 105.34 5431 1.01 272.50 267 11 3.9 EU-155 4.5443-02
0 123.10 16669 1.16 320.19 311 16 1.7 EU-154 7.1573-02
0 247.93 1674 1.29 655.37 648 14 6.9 EU-154 5.9333-02
0 581.75* 122 1.54 1551.95 1544 16 40.3
0 591.79 659 1.84 1578.91 1567 20 9.4 EU-154 6.6613-02
0 661.66 912 1.76 1766.63 1759 19 6.7 CS-137 5.8613-03
0 692.26 331 2.28 1848.84 1839 19 14.1 EU-154 0.105
0 723.31 2398 2.02 1932.25 1921 20 2.8 EU-154 7.0003-02
0 756.74 546 1.84 2022.06 2011 23 9.0 EU-154 7.3103-02
0 873.29 1183 2.19 2335.26 2325 22 4.4 EU-154 6.5813-02
0 996.22 969 2.55 2665.62 2652 25 5.2 EU-154 6.9023-02
0 1004.71 1601 2.30 2688.44 2677 25 3.6 EU-154 6.7453-02
0 1173.24 1723 2.53 3141.44 3127 28 2.9 c0-60 1.4653-02
1 1244.87 41 2.77 3334.00 3327 21 29.8 3.013+00
1 1246.73 55 2.78 3339.00 3327 21 25.7
0 1274.46 2495 2.68 3413.56 3396 30 2.1 EU-154 6.4613-02
0 1332.45 1551 3.10 3569.46 3552 29 2.6 c0-60 1.4573-02
1 1595.19 66 3.08 427.6.00 4266 22 18.4 2.653+00
1 1597.42 71 3.08 4282.00 4266 22 14.1 EU-154 4.343E-02
Minimum Detectable Activity Report
Bckgnd Energy MDA
Nuclide Sum (keW (uCi/sample)
BE-7 665. 477.61 4.85813-03
K-40 9. 1460.83 1.32973-03
MN-54 273. 834.84 5.03703-04
CO-58 318. 810.78 5.34233-04
FE-59 213. 1099.25 9.74063-04
SR-85 694. 514.00 5.70483-04
NE-94 1387. 871.09 1.17313-03
NB-95 370. 765.81 5.50183-04
RU-103 588. 497.05 5.52903-04
RURH-10 6 421. 621.92 5.08003-03
AG- 108M 2702. 722.90 1.55373-03
SB-125 663. 427.88 1.56383-03
SNSB-126 450. 666.30 5.45243-04
CS-134 358. 795.86 6.50303-04
CE-139 4305. 165.85 7.22613-04
CE-141 5547. 145.44 1.29103-03
CEPR-144 6365. 133.54 5.88503-03
EU-152 43. 1408.01 1.42893-03
HG-203 10469. 72.87 1.77953-02
RA-226P 929. 351.93 1.22813-03
-
TH 232P 2230. 238.63 1.20673-03
RPP-7806 Rev. 0 11-D
- I_._-
Minimum Detectable Activity Report (continued) Page : 4
Sample ID : A2 23/4inch L by Acquisition date : 23-JAN-2001 15:55:36
Bckgnd Energy MDA
Nuclide SUm (kev) /
(uCi s amp1e )
U-2355 3594. 185.71 9.79083-04
U-238s 1230. 1001.03 1.46643-01
RF'P-7806 Rev. 0 12-D
BATTELLE / PACIFIC NORTHWEST NATIONAL LAB c 30-JAN-2001 08:22:12.41
RADIOCHEMICAL PROCESSING LABORATORY (325 BLDG.) GAMMA ENERGY ANALYSIS
RADIOANALYTICAL APPLICATIONS TEAM (GEA)
Li/&kar
P W N
Sample Title: A2 piece of lead w/spot / Mauser F21838
-G3775.CNF;l
Config. File: DKA2OO:[USER.SCUSR.ARCHIVEISMP
Analys. File: ND-SC-ASF:COMMON.ASF q ' b 1.31 "1
Effie. File : DKA200: [USER.SCUSR.EFF]EFF-G3GSVZMLW-RT
Library File: nd-sc-1ib:common.nlb
Backgnd File: BKG-G3GSVlOMLW.CNF;38 - 5-JAN-2001 11:39:05.
Acquisition time : 29-JAN-2001 09:18:48 Sample quantity: 1.00000E+00 samp
Sample (EOI) time: 29-JAN-2001 09:18:48 Sample geometry: P3-GSV-2ML-W
Elapsed live time: 0 14:OO:OO.OO
Elapsed real time: 0 14:00:06.79 0.0%
Peak Search Sens.: 5.00000
Eng. Tol. (FWHM) : 0.75 Half life ratio: 8.00
Errors propagated: Yes Systematic Erro: 1.30
Abundance limit : 70.00 WTM error limit: 3.00
Analyses by : PEAK V16.6 PEAKEFF V2.2 ENBACK V1.5 NID V3.2
WTMEAN V1.8 MINACT V2.5
Nuclide Line Activity Report
Nuclide Type: Natural
Uncorrected Decay Corr 1-Sigma
Nuclide Energy %Abn %Ef f uCi/samp uCi/samp %Error Status
K-40 1460.83 10.67* 2.9703-01 2.4673-04 2.4673-04 27.26 OK
Final Mean for 1 Valid Peaks = 2.4673-04+/- 6.7233-05 ( 27.26%)
Nuclide Type: Fission
Uncorrected Decay Corr 1-Sigma
Nuclide Energy %Abn %Ef f uCi/samp uCi/samp %Error Status
CS-137 661.66 85.20" 5.4843-01 2.1423-05 2.1423-05 19.17 OK
Final Mean for 1 Valid Peaks = 2.1423-05+/- 4.107E-06 ( 19.17%)
Flag: "*" = Keyline
WP-7806 Rev. 0 13-D
Post-NID Peak Search Report : Page : 2
Sample ID : A2 piece of le Acquisition date : 29-JAN-2001 09:18:48
It Energy Area FWHM Channel Left Pw %Err Fit Nuclides Activity
uCi/ samp
5 516.13 102 2.35 1375.85 1353 30 43.4 1.413+00
0 661.50 187 1.67 1766.38 1760 15 19.1 CS-137 2.1423-05
0 1461.15* 146 3.56 3915.84 3898 43 27.2 K-40 2.4673-04
Minimum Detectable Activity Report
Bckgnd Energy MDA
Nuclide SUm (keW (uCi/samp)
BE-7 546. 477.61 7.89183-05
MN-54 211. 834.84 7.91023-06
CO-58 219. 810.78 7.95243-06
FE-59 160. 1099.25 1.51563-05
CO-60 147. 1332.50 9.44953-06
SR-85 1002. 514.00 1.22803-05
NB-94 235. 871.09 8.62353-06
NB-95 290. 765.81 8.74383-06
RU-103 501. 497.05 9.15993-06
RURH-10 6 310. 621.92 7.78953-05
AG-10 8M 282. 722.90 8.96903-06
SB-125 680. 427.88 2.82873-05
SNSB-126 312. 666.30 8.10653-06
CS-134 246. 795.86 9.62023-06
CE-139 1679. 165.85 8.07033-06
CE-141 1781. 145.44 1.31443-05
CEPR-144 1707. ' . 133.54 5.44563-05
EU-152 89. 1408.01 3.66643-05
EU-154 137. 1274.44 2.51993-05
EU-155 1549. 105.31 2.73453-05
HG-203 1491. 72.87 1.20453-04
RA-226P 925. 351.93 2.18833-05
TH-2 32P 1620. 238.63 1.83663-05
U-235s 2007. 185.71 1.30673-05
U-238s 217. 1001.03 1.10013-03
AM-241 965. 59.54 2.40373-05
RPP-7806 Rev. 0 14-D
Battelle Pacific Northwest National Laboratory Project 42161
Radiochemical Processing Group - 325 R. Mauser
2/21/01
Decontamination of Coatings by Procedure ASTM D 4256, and RPP-7531
Two samples of the gray polyurea material were received from R. Mauser for
decontamination testing according to ASTM procedure in RPP-7531. By agreement with
the client, Hanford tank waste from tank AN107 was used for the testing in place of
standards. The samples were only exposed to the tank waste as per part A of the
procedure, and then decontaminated in water. Gamma counting was performed following
each treatment. The listed I-sigma uncertainties only refer to the relative counting results.
Absolute values have a higher uncertainty due to the non-standard geometry of the
specimens. Water decon results show that all activities were removed to MDA limits
except for Cs-137.
Sample D -Part A Testing -Water Decon
Activities are listed in microcuries per sample
Sample 1 Sample 2
I Isotope Initial Water DF ]I Initial Water DF
CO-60 1.333-2 < 8.63-6 > 1550 1.333-2 < 7.73-6 > 1727
+I- 2% +I- 2 %
CS-137 5.153-3 3.813-5 135 5.583-3 2.653-5 211
+I- 5 % +I- 12% +I- 5% +I- 25%
Eu-154 6.193-2 < 2.43-5 > 2623 6.163-2 < 2.23-5 > 2800
+I- 2% +I- 2 %
Eu-155 4.133-2 < 2.53-5 > 1672 4.053-2 < 2.53-5 > 1620
+I- 3 % +I- 3 %
Am-241 7.163-2 < 2.33-5 > 3127 7.063-2 < 2.33-5 > 3070
+I- 4 % +/- 4 %
RPP-7806 Rev. 0 15-D
BATTELLE / PACIFIC NORTHWEST NATIONAL LAB 14-FEB-2001 12:28:48.19
RADIOCHEMICAL PROCESSING LABORATORY (325 ELDG.) GAMMA ENERGY ANALYSIS
RADIOANALYTICAL APPLICATIONS TEAM (GEA)
Sample Title: D1 with Spot/Mauser
-
Config. File: DKA200: [USER.SCUSR.ARCHIVEISMP G3810.CNF;l
Analys. File: ND-SC-ASF:COMMON.ASF
Effic. File : DKA2OO:[USER.SCUSR.EFFlEFF -G3GSV2MLW-RT
Library File: nd-sc-1ib:comon.nlb
Backgnd File: DKA200: [USER.SCUSR.ARCHIVElBKG-G3GSVZMLW.CNF;33 - 9-FEB-2001 14:25
Acquisition time : 14-FEE-2001 11:58:17 Sample quantity: 1.00000E+00 sa
Sample (EOI) time: 14-FEE-2001 11:58:16 Sample geometry: P3-GSV-ZML-W
Elapsed live time: 0 00:30:00.00
Elapsed real time: 0 00:30:20.22 1.1%
Peak Search Sens.: 5.00000
Eng. Tol. (FWHM) : 0.75 Half life ratio: 8.00
Errors propagated: Yes Systematic Erro: 1.30
Abundance limit : 70.00 WTM error limit: 3.00
Analyses by : PEAK V16.6 PEAKEFF V2.2 ENBACK V1.5 NID V3.2
WTMEAN V1.8 MINACT V2.5
Nuclide Line Activity Report
Nuclide Type: Activation
Uncorrected Decay Corr 1-Sigma
Nuclide Energy %Abn %Ef f uCi/sa .. uCi/sa %Error Status
CO-60 1173.24 99.97 3.5343-01 1.2973-02 1.2973-02 2.56 OK
1332.50 99.99* 3.199E-01 1.3643-02 1.3643-02 2.31 OK
2505.74 - - Miscellaneous-- ----- Line Not Found - - - - - Absent
Final :.lean f o r 2 Valid Pea!cs :
: 1.332E-O2t/- 2.290E-04 ( 1.724)
Nuclide Type: Fission
Uncorrected Decay Corr 1-Sigma
Nuclide Energy %Abn %Ef f uCi/sa uCi/sa %Error Status
CS-137 661.66 85.20* 5.484E-01 5.1503-03 5.1503-03 4.66 OK
Final Mean for 1 Valid Peaks = 5.1503-03+/- 2.40lE-04 ( 4.66%)
EU-154 123.07 40.60 1.7233+00 6.3423-02 6.3423-02 1.99 OK
247.93 6.91 1.2263+00 5.923E-02 5.9233-02 4.23 OK
591.76 4.96 5.992E-01 6.054E-02 6.0543-02 6.08 OK
692.42 1.79 5.2933-01 6.3043-02 6.3043-02 15.03 OK
723.30 20.11 5.1153-01 6.0293-02 6.0293-02 2.76 OK
756.80 4.54 4.9393-01 6.3963-02 6.3963-02 6.89 OK
RF'P-7806 Rev. 0 ;
16-D
Nuclide Line Activity Report (continued) Page : 2
Sample ID : D1 with Spot/M Acquisition date : 14-FEB-2001 11:58:17
Nuclide Type: Fission
Uncorrected Decay Corr 1-Sigma
Nuclide Energy %Abn %Eff uCi/sa uCi/sa %Error Status
873.19 12.20 4.4263-01 6.2253-02 6.2253-02 3.53 OK
996.26 10.53 4.0043-01 6.5293-02 6.5293-02 3.94 OK
1004.25 17.91 3.9783-01 6.1893-02 6.1893-02 3.00 OK
1274.44 35.00* 3.3143-01 6.1223-02 6.1223-02 2.19 OK
1596.49 1.79 2.7583-01 5.9283-02 5.9283-02 8.16 OK
Final Mean for 11 Valid Peaks = 6.1923-02+/- 6.2853-04 ( 1.02%)
EU-155 60.01 1.13 8.9793-01 2.2763+00 2.2763+00 5.76 <<WM Interf
86.54 30.85 1.5283+00 4.0913-02 4.0913-02 4.37 OK
105.31 21.20* 1.6933+00 4.1733-02 4.1733-02 4.03 OK
Final Mean f o r 2 Valid Peaks = 4.1343-02+/- 1.2253-03 ( 2.96%)
Nuclide Type: fission
Uncorrected Decay Corr 1-Sigma
Nuclide Energy %Abn %Eff uCi/sa uCi/sa % E r r o r Status
AM-241 59.54 35.90* 8.9793-01 7.1643-02 7.1643-02 4.04 OK
Final Mean f o r 1 Valid Peaks = 7.1643-02+/- 2.8963-03 ( 4.04%)
Flag: "*" = Keyline
RPP-7806 Rev. 0 , 17-D
Post-NID Peak Search Report Page : 3
Sample ID : D1 with Spot/M Acquisition date : 14-FEB-2001 11:58:17
It Energy Area FWHM Channel Left Pw %Err Fit Nuclides Activity
uCi/sa
0 42.79 3117 1.51 104.66 100 10 7.1
0 48.82 971 1.56 120.83 117 9 22.3
0 59.54 15379 1.11 149.63 143 13 2.2 AM-241 7.1643-02
EU-155 2.28
0 86.53 12844 1.12 222.11 217 12 2.5 EU-155 4.0913-02
0 105.31 9976 1.13 272.52 267 12 2.8 EU-155 4.1733-02
0 123.08 29543 1.15 320.24 311 16 1.1 EU-154 6.3423-02
0 247.93 3342 1.29 655.55 649 13 4.0 EU-154 5.9233-02
0 444.11 124 0.92 1182.50 1178 11 48.3
0 511.20* 396 2.15 1362.75 1355 20 22.6
0 591.71 1198 1.58 1579.07 1570 17 5.9 EU-154 6.0543-02
0 661.60* 1602 1.91 1766.85 1759 16 4.5 CS-137 5.1503-03
0 692.14 398 1.53 1848.92 1841 17 15.0 EU-154 6.3043-02
0 723.27 4130 2.06 1932.58 1922 22 2.3 EU-154 6.0293-02
0 756.73 955 2.06 2022.50 2012 22 6.7 EU-154 6.3963-02
0 873.16 2239 2.25 2335.42 2322 25 3.2 EU-154 6.2253-02
0 996.19 1834 2.55 2666.12 2653 24 3.7 EU-154 6.5293-02
0 1004.82 2937 2.48 2689.32 2678 26 2.6 311-154 6.1893-02
0 1173.17 3051 2.66 3141.92 3126 30 2.2 CO-60 1.2973-02
0 1246.51 96 2.24 3339.13 3325 22 26.5
0 1274.41 4729 2.73 3414.15 3396 37 1.5 EU-154 6.1223-02
0 1332.41 2905 3.03 3570.12 3553 31 1.9 CO-60 1.3643-02
0 1398.01 45 3734 20 30.9
2 1494.10 56 2.96 4005.00 3994 21 17.3 8. 87E-01
2 1495.68 22 2.40 4009.24 3994 21 37.3
0 1596.60 195 2.80 4280.72 4268 24 8.0 EU-154 5.9283-02
Minimum Detectable Activity Report
Bckgnd Energy MDA
Nuclide SUm (keV) (uCi/sa)
BE-7 1180. 477.61 3.23543-03
K-40 25. 1460.83 1.1015E-03
MN-54 533. 834.84 3.52163-04
CO-58 ' 579. 810.78 3.60713-04
FE-59 396. 1099.25 6.64393-04
SR-85 1226. 514.00 3.79213-04
NB-94 2589. 871.09 8.0132E-04
NB-95 626. 765.81 3.57873-04
RU-103 1044. 497.05 3.68383-04
R U M - 10 6 747. 621.92 3.38233-03
AG-108M 4764. 722.90 1.03163-03
SB-125 1311. 427.88 1.09933-03
SNSB-126 783. 666.30 3.59603-04
CS-134 594. 795.86 4.18763-04
CE-139 6394. 165.85 4.40343-04
CE-141 8133. 145.44 7.81733-04
CEPR-144 9234. 133.54 3.54423-03
EU-152 69. 1408.01 9.04723-04
HG-203 15731. 72.87 1.09073-02
RPP-7806 Rev. 0 18-D
Minimum Detectable Activity Report (continued) Page : 4
Sample ID : D1 with Spot/M Acquisition date : 14-FEB-2001 11:58:17
Bckgnd Energy MDA
Nuclide SUm (keV) (uci/sa)
FA-226P 1540. 351.93 7.90553-04
TH-23 2 P 3456. 238.63 7.51163-04
U-2355 5451. 185.71 6.02923-04
U-238s 2204. 1001.03 9.81493-02
RPP-7806 Rev. 0 19-D
BATTELLE / PACIFIC NORTHWEST NATIONAL LAB , 14-FEB-2001 13:01:13.42
RADIOCHEMICAL PROCESSING LABORATORY (325 BLDG.) GAMMA ENERGY ANALYSIS
RADIOANALYTICAL APPLICATIONS TEAM (GEA)
Sample Title: D2 with spot /Mauser 4
4
Config. File: DKA2OO:[USER.SCUSR.ARCHIVE]SMP -G3811.CNF;l I
Analys. File: NE-SC-ASF:COMMON.ASF
Effic. File : DKA2OO:[USER.SCUSR.EFF]EFF -G3GSV2MLW-RT
Library File: nd-sc-1ib:common.nlb
Backgnd File: DKAZOO:[USER.SCUSR.ARCHIVEIBKG -G3GSVZMLW.CNF;33 - 9-FEB-2001 14:25
Acquisition time : 14-FEB-2001 12:30:43 Sample quantity: 1.00000E+00 sa
Sample ( E O I ) time: 14-FEB-2001 12:30:42 Sample geometry: P3-GSV-2ML-W
Elapsed live time: 0 00:30:00.00
Elapsed real time: 0 00:30:20.17 1.1%
Peak Search Sens.: 5.00000
Eng. Tol. (FWHM) : 0.75 Half life ratio: 8.00
Errors propagated: Yes Systematic Erro: 1.30
Abundance limit : 70.00 WTM error limit: 3.00
Analyses by : PEAK V16.6 PEAKEFF V2.2 ENBACK V1.5 NID V3.2
WTMEAN V1.8 MINACT V2.5
Nuclide Line Activity Report
Nuclide Type: Activation
Uncorrected Decay Corr 1-Sigma
Nuclide Energy %Abn %Ef f uCi/sa uCi/sa %Error Status
CO-60 1173.24 99.97 3.5343-01 1.2893-02 1.2893-02 2.50 OK
1332.50 99.99* 3.1993-01 1.3703-02 1.3703-02 2.34 OK
2505.74 - - Miscellaneous-- - - - - - Line Not Found - - - - - Absent
Final Mean for 2 Valid Peaks = 1.3303-02+/- 2.2713-04 ( 1.71%)
Nuclide Type: Fission
Uncorrected Decay Corr 1-Sigma
Nuclide Energy %Abn %Eff uci/sa uCi/sa %Error Status
CS-137 661.66 85.20* 5.4833-01 5.5843-03 5.5843-03 4.23 OK
Final Mean for 1 Valid Peaks = 5.5843-03+/- 2.3613-04 ( 4.23%)
EU-154 123.07 40.60 1.7233+00 6.2493-02 6.2493-02 1.96 OK
247.93 6.91 1.226Ec00 6.0903-02 6.0903-02 3.90 OK
591.76 4.96 5.9913-01 6.5293-02 6.5293-02 6.13 OK
692.42 1.79 5.291E-01 5.6063-02 5.6063-02 18.30 OK
723.30 20.11 5.114E-01 6.1263-02 6.1263-02 2.81 OK
756.80 4.54 4.9393-01 6.1333-02 6.1333-02 6.88 OK
RPP-7806 Rev. 0 20-D
Nuclide Line Activity Report (continued) Page : 2
Sample ID : D2 with spot / Acquisition date : 14-FEB-2001 12:30:43
Nuclide Type: Fission
Uncorrected Decay Corr 1-Sigma
Nuclide Energy %Abn %Ef f uCi/sa uCi/sa %Error Status
873.19 12.20 4.4263-01 5.8763-02 5.8763-02 3.38 OK
996.26 10.53 4.0043-01 6.2893-02 6.2893-02 3.66 OK
1004.25 17.91 3.9783-01 6.3313-02 6.3313-02 2.72 OK
1274.44 35.00* 3.3143-01 5.9973-02 5.9973-02 2.23 OK
1596.49 1.79 2.7583-01 6.9583-02 6.9583-02 7.22 OK
Final Mean for 11 Valid Peaks = 6.1613-02+/- 6.0983-04 ( 0.99%)
EU-155 60.01 1.13 8.9933-01 2.2433+00 2.2433+00 5.68 CCWM Interf
86.54 30.85 1.5293+00 4.1863-02 4.1863-02 4.25 OK
105.31 21.20* 1.6933+00 3.9283-02 3.9283-02 4.18 OK
Final Mean for 2 Valid Peaks = 4.0473-02+/- 1.2063-03 ( 2.98%)
Nuclide Type: fission
Uncorrected Decay Corr 1-Sigma
Nuclide Energy %Abn %Eff uCi/sa uCi/sa %Error Status
AM-241 59.54 35.90* 8.9933-01 7.0603-02 7.0603-02 3.93 OK
Final Mean for 1 Valid Peaks = 7.0603-02+/- 2.7733-03 ( 3.93%)
Flag: “*‘I = Keyline
WP-7806 Rev. 0 21-D
Post-NID Peak Search Report ', Page : 3
Sample ID : D2 with spot / Acquisition date : 14-FEB-2001 12:30:43
It Energy Area FWHM Channel Left Pw %Err Fit Nuclides Activity
uci/sa
0 42.77 2893 1.38 104.60 99 11 8.3
0 49.10 1496 1.04 121.59 117 12 18.4
0 59.58 15180 1.06 149.75 145 11 2.0 AM-241 7.060E-02
EU-155 2.24
0 86.56 13148 1.12 222.18 2 17 11 2.2 EU-155 4.186E-02
0 105.31 9390 1.13 272.55 267 12 3.0 EU-155 3.9283-02
0 123.10 29111 1.17 320.31 313 14 1.1 EU-154 6.2493-02
0 247.98 3436 1.34 655.68 650 12 3.7 EU-154 6.090E-02
0 444.31 241 0.98 1183.05 1178 10 21.2
0 511.39* 421 2.58 1363.26 1355 18 19.4
0 582.07* 342 1.25 1553.16 1545 16 18.0
0 591.81 1292 1.88 1579.31 1570 20 5.9 EU-154 6.5293-02
0 661.68* 1737 1.81 1767.05 1759 17 4.0 CS-137 5.5843-03
0 692.45 354 2.01 1849.75 1841 18 18.2 EU-154 5.6063-02
0 723.31 4196 2.05 1932.69 1921 24 2.4 EU-154 6.1263-02
0 756.75 916 2.16 2022.55 2012 20 6.7 EU-154 6.1333-02
0 873.20 2113 1.95 2335.52 2325 19 3.1 EU-154 5.8763-02
0 903.94 i6n 2.46 2418.13 2409 17 26.1
1 996.37 1766 2.58 2666.60 2650 55 3.1 1.73E+00 EU-154 6.2893-02
1 1004.79 3004 2.55 2689.23 2650 55 2.3 EU-154 6.3 3 1E-02
0 1173.26 3033 2.68 3142.16 3127 28 2.1 CO-60 1.289E-02
0 1274.44 4632 2.85 3414.23 3398 36 1.6 EU-154 5.9973-02
0 1332.44 2918 2.97 3570.19 3553 28 1.9 CO-60 1.3703-02
0 1398.89 25 2.08 3748.90 3734 18 50.8
0 1493.65 101 2.39 4003.77 3991 22 10.7
2 1594.45 47 3.38 4274.92 4268 24 26.1 1.72E+00
2 1596.59 229 3.00 4280.68 4268 24 7.1 EU-154 6.9583-02
Minimum Detectable Activity Report
Bckgnd Energy MDA
Nuclide Sum (keV) (uci/sa)
BE-7 1135. 477.61 3.17233-03
IC-40 31. 1460.83 1.21863-03
MN-54 517. 834.84 3.46533-04
CO-58 546. 810.78 3.50333-04
FE-59 367. 1099.25 6.39923-04
SR-85 1208. 514.00 3.76383-04
NB-94 2481. 871.09 7.84363-04
NB-95 612. 765.81 3.53583-04
RU-103 1029. 497.05 3.65733-04
RURH-10 6 756. 621.92 3.40113-03
AD-1O8M 4795. 722.90 1.03493-03
SB-125 1315. 427.88 1.1011E-03
SNSB-126 833. 666.30 3.7107E-04
CS-134 619. 795.86 4.27553-04
CE-139 6439. 165.85 4.41923-04
CE-141 7863. 145.44 7.68663-04
CEPR-144 9109. 133.54 3.52013-03
EU-152 ' 79. 1408.01 9.66253-04
RPP-7806 Rev. 0 22-D
Minimum Detectable Activity Report (continued) Page : 4
Sample ID : D2 with spot / Acquisition date : 14-FEB-2001 12:30:43
Bckgnd Energy MDA
Nuclide Sum (kev) (uCi/sa)
HG-203 15596. 72.87 1.08603-02
RA-226P 1679. 351.93 8.25333-04
TH-23 2P 3497. 238.63 7.55543-04
U-235s 5327. 185.71 5.96023-04
U-2385 2234. 1001.03 9.88173-02
RF'P-7806 Rev. 0 23-D
bATTELLE / PACIFIC NORTHWEST NATIONAL LAB , 16-FEB-2001 07:31:55.75
RADIOCHEMICAL PROCESSING LABORATORY (325 BLDG.) GAMMA ENERGY ANALYSIS
RADIOANALYTICAL APPLICATIONS TEAM (GEA)
Sample Title: D1 Decon with DDI Water 2/15/01 Mauser
Config. File: DKAZOO:[USER.SCUSR.ARCHIVEISMP -G3819.CNF;l
!
p 1J/16'o 'J
Analys. File: N D-SC-ASF:COMMON.ASF
Effie. File : DKA2OO:[USER.SCUSR.EFFIEFF -G3GSVZMLW-RT
Library File: nd-sc-1ib:common.nlb
Backgnd File: DKA200: tUSER.SCUSR.ARCHIVElBKG-G3GSVZMLW.CNF;33 - 9-FEB-2001 14:25
Acquisition time : 15-FEB-2001 15:27:49 Sample quantity: 1.00000E+00 sa
Sample (EOI) time: 15-FEB-2001 15:27:49 Sample geometry: P3-GSV-2ML-W
Elapsed live time: 0 16:OO:OO.OO
Elapsed real time: 0 16:00:07.52 0.0%
Peak Search Sens.: 5.00000
Eng. Tol. (FWHM) : 0.75 Half life ratio: 8.00
Errors propagated: Yes Systematic Erro: 1.30
Abundance limit : 70.00 WTM error limit: 3.00
Analyses by : PEAK V16.6 PEAKEFF V2.2 ENBACK V1.5 NID V3.2
WTMEAN V1.8 MINACT V2.5
Nuclide Line Activity Report
Nuclide Type: Fission
Uncorrected Decay Corr 1-Sigma
Nuclide Energy %Abn %Ef f uCi/sa uCi/sa %Error Status
CS-137 661.66 85.20* 5.4843-01 3.8083-05 3.8083-05 12.12 OK
Final Mean for 1 Valid Peaks = 3.8083-05+/- 4.6163-06 ( 12.12%)
Flag: 'I*" = Keyline
RPP-7806 Rev. 0 24-D
Post-NID Peak Search Report ? Page : 2
Sample ID : D1 Decon with Acquisition date : 15-FEB-2001 15:27:49
It Energy Area FWHM channel Left Pw %Err Fit Nuclides Activity
uCi/sa
0 661.53* 379 1.58 1766.73 1760 15 12.1 1.933+00 CS-137 3.808E-05
Minimum Detectable Activity Report
Bckgnd Energy MDA
Nuclide SUm (keW (uCi/sa)
BE-7 653. 477.61 7.55323-05
K-40 474. 1460.83 1.49833-04
MN-54 255. 834.84 7.62133-06
CO-58 241. 810.78 7.29753-06
FE-59 165. 1099.25 1.34513-05
CO-60 158. 1332.50 8.57633-06
SR-85 1093. 514.00 1.12273-05
NB-94 236. 871.09 7.55733-06
NB-95 281. 765.81 7.53613-06
RU-103 631. 497.05 8.99843-06
RURH - 1.06 361. 67.3.. 9 2 7.351RE-05
AG-108M 306. 722.90 8.17233-06
SB-125 717. 427.88 2.54123-05
SNSB-126 321. 666.30 7.19503-06
CS-134 230. 795.86 8.15023-06
CE-139 1760. 165.85 7.23083-06
CE-141 1907. 145.44 1.13113-05
CEPR-144 1834. 133.54 4.9396E-05
EU-152 135. " 1408.01 3.93833-05
EU-154 158. 1274.44 2.36233-05
EU-155 1647. 105.31 2.46763-05
HG-203 1696. 72.87 1.12453-04
RA-226P 1036. 351.93 2.0259E-05
TH-2 3 2 P 1722. 238.63 1.65683-05
U-235s 2246. 185.71 1.20333-05
U-238.5 218. 1001.03 9.65623-04
AM-241 1141. 59.54 2.28673-05
RPP-7806 Rev. 0 25-D
---
BATTELLE / PACIFIC NORTHWEST NATIONAL LAB 20-FEB-2001 08:22:20.54
RADIOCHEMICAL PROCESSING LABORATORY (325 BLDG.) GAMMA ENERGY ANALYSIS
RADIOANALYTICAL APPLICATIONS TEAM (GEA)
Sample Title: D2 Decon w/ DDI / Mauser F21838
Config. File: DKA2OO:[USER.SCUSR.ARCHIVE]SMP -G3836.CNF;l
Analys. File: ND-SC-ASF:COMMON.ASF
Effie. File : DKAZOO:[USER.SCUSR.EFF]EFF-G3GSV2MLW -RT
Library File: nd-sc-1ib:common.nlb
Backgnd File: BKG-G3GSV2MLW.CNF;33 - 9-FEB-2001 14:25:51.
Acquisition time : 19-FEB-2001 16:00:32 Sample quantity: 1.00000E+00 sample
Sample (EOI) time: 19-FEB-2001 16:00:32 Sample geometry: P3-GSV-2ML-W
Elapsed live time: 0 16:OO:OO.OO
Elapsed real time: 0 16:00:07.67 0.0%
Peak Search Sens.: 5.00000
Eng. Tol. (FWHM) : 0.75 Half life ratio: 8.00
Errors propagated: Yes Systematic Erro: 1.30
Abundance limit : 70.00 WTM error limit: 3.00
Analyses by PEAK V16.6 PEAKEFF V2.2 ENBACK V1.5 NID V3.2
WTMEAN V1.8 MINACT V2.5
Nuclide Line Activity Report
Nuclide Type: Natural
Nuclide
K-40
Energy
1460.83
Final Mean for
%Abn
10.67*
%Eff
2.9703-01 1.0673-04
1 Valid Peaks = 1.0673-04+/-
Ygm
Uncorrected Dccay Corr 1-
uCi/sample uCi/sample
1.067E-
Error
48.36
.161E-05 ( 48.36%)
Status
OK
Nuclide Type: Fission
Uncorrected Decay Corr 1-Sigma
Nuclide Energy %Abn %Eff uCi/sample uCi/sample %Error Status
CS-137 661.66 85.20* 5.4833-01 2.6473-05 2.6473-05 24.48 OK
Final Mean for 1 Valid Peaks = 2.6473-05+/- 6.4803-06 ( 24.48%)
Flag: 'I*'' = Keyline
RPP-7806 Rev. 0 26-D
_I_- "-
Post-NID Peak Search Report Page : 2
Sample ID : D2 Decon w/ DD Acquisition date : 19-FEB-2001 16:00:32
It Energy Area FWHM Channel Left Pw %Err Fit Nuclides Activity
uci / sample
0 661.70* 264 1.83 1767.01 1754 26 24.4 6.363-01 CS-137 2.6473-05
0 1460.97* 72 3.43 3915.62 3904 22 48.3 K-40 1.0673-04
1 2613.70* 27 :1
38 701@.00 6999 29 63.4 2.853+00
Minimum Detectable Activity Report
Bckgnd Energy MDA
Nuclide SUm (keW (uCi/sample)
BE-7 620. 477,61 7.35823-05
MN-54 248. 834.84 7.50673-06
CO-58 254. 810.78 7.49363-06
FE-59 236. 1099.25 1.60923-05
CO-60 127. 1332.50 7.68643-06
SR-85 1166. 514.00 1.15943-05
NB-94 272. 871.09 8.11913-06
NB-95 290. 765.81 7.66293-06
RU-103 638. 497.05 9.05333-06
RURH-10 6 380. 621.92 7.54643-05
AG- 10 8M 323. 722.90 8.39243-06
SB-125 757. 427.88 2.61103-05
SNSB - 126 335. 666.30 7.35353-06
CS-134 270. 795.86 8.81873-06
CE-139 1933. 165.85 7.57903-06
CE-141 1933. 145.44 1.19913-05
CEPR-144 1878. 133.54 4.99833-05
EU-152 127. 1408.01 3.82213-05
EU-154 138. 1274.44 2.20933-05
EU-155 1663. 105.31 2.47963-05
HG-203 1624. 72.87 1.3.0053-04
RA-226P 1087. 351.93 2.07493-05
TH-232P 1811. 238.63 1.69903-05
U-235s 2181. 185.71 1.19183-05
U-238s 218. 1001.03 9.65773-04
AM-241 1139. 59.54 2.28493-05
RPP-7806 Rev. 0 27-D
i
Testing Apparatus for Decontainination Factor Testing
RPP-7806 Rev. 0 28-D
Assembled Dccontainination Factor Test Holder
Top View
KPP-7806 Kcv. 0
.’. . _ _ I
. .
Factoi- Test I lolder
Asseniblcd I~ccoti~aiiiiiiatioii
Sidc View
RPP-7806 Kcv. 0
Decontamination Factor Test Apparatus for
Stippled Over Spray Finish on
Polyurea Test Coupon
Assembled Decontamination Factor Testing Apparatus
for
Stippled Finish Polyurea Test Coupon
Side View
RPP-7806 Rev. 0 32-D
_ _ ~ ~
~
__~ - .. -~
. ~
\
Assembled Decontamination Factor Testing Apparatus
for
~ - .
Stippled Finish Polyurea Test Coupon
Top View
RPP-7806 Rev. 0
33-D
APPENDIX E
DECONTAMINTATION
FACTOR (DF)
CALIBRATION
SPREADSHEETS
RPP-7806 Rev. 0 1-E
~~. ~ ~~ ., .~
~~ ~ ~
---
---. ~ ~~
___.- -~..~
'?
VMS Calibration Report V1.5 Generated 14-FEB-2001 15:34:18
Configuration : DKA2OO:[GAMMA.EFFlEFF -G5PVL-lOl.CNF;l
Analyses by : CALIBRATE V1.7
Detector Name : G Energy Calib Time: 16-MAY-1997 08:05:38
Efficiency type : Empirical Effncy Calib Time: 19-MAY-1997 03:10:12
Detector Geometry: P5-PVL Shelf : 5 ,
Efficiency Calibration Report
Eff P exp(a2 + a3*x + a4*x**2 + a5*x**3 + a6*x**4 + a7*x**5). x=ln(al/energy)
al.. . a2 a3 a4 a5 a6 a7
947.8 -7.094 0.7751 -9.69553-03 -3.80383-03 2.38513-02 -1.68033-02
Average Deviation = 1.08 % Reduced Chi-square = 5.98
Energy Measured Efficiency Computed Dif f /
Nbr (keV) Efficiency Error Efficiency /Error % Diff
1 59.54 1.613-03 1.323-05 1.613-03 0.33 02 7
2 88.03 2.793-03 2.653-05 2.823-03 -1.05 -1.00
3 122.06 3.123-03 2.693-05 3.133-03 -0.59 -0.51
4 165.85 2.963-03 2.553-05 2.903-03 2.47 2.12
5 279.20 2.073-03 2.453-05 2.113-03 -1.82 -2.16
6 391.69 1.633-03 2.883-05 1.643-03 -0.18 -0.32
7 514.01 1.313-03 1.293-05 1.333-03 -1.57 -1.55
8 661.66 1.103-03 9.523-06 1.103-03 0.74 0.64
9 898.04 8.773-04 . 1.523-05 8.653-04 0.77 1.33
10 1173.24 7.113-04 2.613-06 7.033-04 3.01 1.11
11 1332.50 6.293-04 2.273-06 6.373-04 -3.43 -1.23
12 1836.06 5.033-04 3.443-06 4.993-04 1.09 0.75
Approved by: v---+- ! Approval Date: 3/ Lr/ "/
RPP-7806 Rev. 0
2-E
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__ I
APPENDIX F
DECONTAMINTATION
FACTOR (DF)
TESTING
CONTRACT
WITH
PNNL
RPP-7806 Rev. 0 I -F
Pacific Northwest
National Laboratory
Operated by Battelle for the
US. Department of Energy
February 15,2001
Mr. Robert W. Mauser
CH2M Hill Hanford Group Inc.
MS H6-16
2400 Stevens Center
P. 0. Box 1500
Richland, WA 99352
Subject: DST W-314 Polpurea Tesdne. ContIact 00008247. Release 00036 - PNNL Proiect 42161
& .
Dear I Mauser:
Work has been completed on the subject contract as per our agreement in the statement of work.
Polyurea-coated steel coupons and polyurea samples were tested according to ASTM Procedure
RPP-7531. There were several exceptions to this procedure, as per our agreement. These included
using Hanford waste tank material as the source rather than a prepared standard and having special
holders designed in our shops for the Pact B testing as substitutes for the holders specified in the
ASTM procedure. We further had to modify the procedure for the polyurea samples due to the
paper backing, which interfered with the test. For the first attempt with the polyurea samples, we
sluiced water over the sample for the decon testing rather than immersing the sample since the
paper backing would have retained considerable activity. This method appeared to succeed on one
of the duplicate samples; however, some of the activity did appear to be retained in the paper
backing on the duplicate sample. A new holder was thus designed to fit over the polyurea so .thatwe
could contact the sample with water without soaking the backing paper. Pictures of the holders that
we designed for the tests are attached.
Samules identification: Four identical dark brown-coated metal coupons were received from the
client. They were labeled A-1, A-2, B-1, and B-2. Four pieces of gray polyurea m a t e d with a paper
coated metal backing were cut to the approximate size of the metal coupons and labeled C-1, C-2,
D-1, and D-1. An effort was made to remove the paper backing. This was not entirely successful
on the C samples; however, most of the paper was removed from the D samples processed later.
Samule ureparation: Radioactive material from Hanford waste tank AN107 was obtained from
our hot cells in the Radiochemical Processing Laboratory at PNNL. Multi-range pH paper showed
hs
the material to have a pH of 11. For the Part A testing, aliquots measuring 200 ul of t i material
were pipetted onto coupons A-1 and A-2 in an area about 1 cm in diameter and allowed to dry at
room temperature in a fume hood. They were packaged in separate plastic bags and sealed on the
back with tape, then placed inside another plastic bag and sealed on the back with tape. They were
then Gamma counted.
902 Battelle BouIevard * PO. Box 999 * Richland, WA 99352
RPP-7806 Rev. 0 2-F
Mr. Robert W. Mauser
February 15, 2001
Page 2
Two sample holders were fabricated in our shops for the part B testing. The holders were
assembled using the B-1 and B-2 coupons, as shown in the attached photographs. A 2 ml aliquot of
the tank material was placed into the holder and sealed with the ground glass stopper. These
coupons were allowed to set undisturbed for 7 days in a fumehood. The sample level appeared
unchanged at the end of seven days. The tank material was removed with a tmnsfer pipette. It was
noted on B-2 that a small amount of tank material had seeped from under the gasket and dried on
the coupon. The sample holder was turned upside down and removed. The sample was allowed to
dry to accommodate our counting capabilities. The sample was packaged the same way as A-1 and
'A-2. The polyurea coupons C-1, C-2, D-1, and D-2 were prepared in the same way as A-1 and A-2
except only 100 ul of tank material was used for the C samples due to limited availability of the
sample at the time of testing. Additional tank sample was obtained from the hot cells so that 200 ul
aliquots were used for the D polyurea samples.
DDI SamDle decontamination: At the end of counting A-1, A-2, B-1 and B-2 were suspended
separately in 300 ml tall form beakers. About 250 ml of DDI (deionized water) was added to cover
the coupon well above the contaminated area and mixed with a magnetic stLrer for 10 minutes. The
coupon back was rinsed gently with clean DDI water to remove the contaminated DDI and allowed
to air dry: They were packaged and counted with the same geometry as in the sample preparation.
Samples C-l and C-2 were not covered with water for decontamination. They were rinsed with 200
ml of water dispensed repeatedly with a plastic transfer pipette. Every effort was made to keep the
absorbent paper backing from becoming contaminated. They were packaged and counted as before.
A holder was fabricated in our shops for the D sample decontamination. The holder was placed on
top of the sample, then water was added and stirred, using a plastic mesh to avoid abrasion of the
sample. This method was designed to avoid having any of the solution come in contact with the
back of the sample.
Cold acid decontamination: 250 ml of acid decontamination solution was prepared separately
for each sample. 125 ml of (.1M Sodium Fluoride/.SM Oxalic acid) was added to a 250 ml
volumetric flask. 8.5 ml of 30% Hydrogen Peroxide solution was added and the final volume
was adjusted to 250 ml. This solution was added to the beaker with the coupon suspended in it
and allowed to stir for 10 minutes. The coupon back was gently rinsed with DDI to removethe
contaminated solution, allowed to air dry, and packaged and counted as before. A-1, A-2, B-1
and B-2 were the only coupons decontaminated with acid.
Hot acid decontamination: Since virtually all of the measurable activity was removed either by
water or a cold acid decontamination, the hot acid decontamination was not required.
Results: The results are presented on the attached spreadsheets with a brief narrative to describe
each set of data.
Data and Supporting Documentation: The gamma counting data is included with this data
package. Each count is labeled at the top to identify the sample and step of the procedure. The
report for each sample includes the peak integrations, calculated activities, and minimum
detectable activities for common fission and activation products. The data package also includes
RPP-7806 Rev. 0 3-F
Mr. Robert W. Mauser
February 15, 2001
Page 3
the detector calibration and a control chart that shows the results of a mixed Am-241 and co-60
standard counted daily on days when the detector was in use. All counting was performed on our
G detector. It should be noted that the detector calibration was performed with a point source
standard from NIST. However, the samples typically had an area of about 1 cm in diameter and
the distance between the face of the coupon and the detector was slightly larger than the distance
between our point source standard and the detector. This difference introduces a low bias in our
absolute counting results estimated to be about 5-1 0%. However, since all counting was
performed in the same positions for each coupon, the relative uncertainties, as quoted on the
spreadsheets, are generally only limited by the counting statistics and any absolute calibration
bias cancels out in the DF calculation.
Qualiw Control and Records: This work was conducted according to PNNL’s Standard Based
management System quality control plan “Conducting Analytical Work in Support of Regulatory
Programs”, except as noted above. All original project records will be retained by PNNL for
archival storage.
Sincerely,
Larry R. Greenwood Mahilyn J. Steele
Senior Staff Scientist Senior Technician
Enc - Spreadsheet Tables, Pictures, Gamma Data, and Supporting Documentation.
RPP-7806 Rev. 0 4-F
___._
.
. ~ -. . .___I-..- .
APPENDIX G
GAMMA IRRADIATION
INSTRUMENT
DATA
SPREADSHEET
CALIBRATION
SPREADSHEET
&
PICTURES
RPP-7806 Rev. 0 1-G
co-60 Gamma Irradiation Data Sheet
Tube Number: 16
Customer Name: Robert Mauser
ComDanv Name: Los Alamos Technical Associates
WP Number: F2 1838
Dose Rate (R/hr): 1.69 X 1O5
Test Material Irradiated: Polyurea Coated Concrete Samples
1/24/01 11:47 AM
1124101 11:47 AM 1.0 x io7 Samples
1/26/01 3:34PM #2
1/29/01 7:52 AM 1 1
1129101 4:11 PM
1/26/01 3:34PM I 1.1 x io7 Samples
1129101 7:52AM #3
1/29/01 I 4:11 PM I 1.1 x lo7 Samples
2/1/01 7:39AM #4
RF'P-7806 Rev. 0 2-G
RPP-7806 Rev. 0 3-G
-..- Pacific Northwest Laboratories
Dale December 5 , 1984
T@ G. L . Jones
Fr@m 3. L. Pappin
Suhlect 3730 6OCo FACILITY CALIBRATION
Results f o r the r e c e n t c a l i b r a t i o n of a l l exposure tubes a t t h e
3730 6oCo F a c i l i t y a r e a t t a c h e d . C a l i b r a t i o n data were c o l l e c t e d
from 8/24/84 thru 10/5/84. The c a l i b r a t i o n s were formed using an
i o n chamber and thermoluminescent dosimeters (TLD's).
The ion chamber measurements were made u s i n g a Capintec PR-06C
chamber w i t h build u p cap, S/N CIIG 64053, and a Keithley e l e c t r o -
m e t e r , S/N 115092. The ion chamber i s a t r a n s f e r standard which
c a r r i e s a c a l i b r a t i o n c e r t i f i c a t e for 6OCo from t h e National Bureau
of Standards dated 5/28/82. The c a l i b r a t i o n of this chamber was
confirmed by d i r e c t comparison w i t h a Capintec PM-30 chamber which
carries a c a l i b r a t i o n c e r t i f i c a t e for 6OCo from the National Bureau
of Standards dated 1/25/84. The ion chamber c a l i b r a t i o n measure-
ments were performed i n Tube #21 w i t h the chamber centered 6 , 8,
and 10 inches from the bottom o f the t u b e on 8/24/84, which i s the
o f f i c i a l d a t e of c a l i b r a t i o n f o r a l l t u b e s . Ion chamber c a l i b r a -
t i o n r e s u l t s a r e given i n Table 1.
Table 1: Ion Chamber C a l i b r a t i o n Tube 21, 8/24/84
P o s i t i o n inches from bottom Calibrated l o 5 R/h
6 4.76
8 5.06
10 5.16
RPP-7806 Rev. 0 4-G
. .~
.~~ ".
.... . ..."
~
-_
-. ~ . __ .
.
G. L. Jones
December 5, 1984
Page 2
TLD exposures were made by placing packets containing three TLD
800's inside the center of a 33" long x 1 1/2" diameter p l a s t i c
( l u c i t e ) tube having 32 positions a t 1" i n t e r v a l s . This tube
provides electronic equilibrium and reproducible geometry and i s
shown i n photo # l . The l u c i t e tube has three holes d r i l l e d thru i t
such t h a t p l a s t i c rods may be inserted f o r alignment a t the center
a t the 6oCo exposure tubes. During TLD exposures the l u c i t e tube
containing TLD 800 packets i s lowered down until i t r e s t s on the
bottom and i n the center of a 6oCo exposure tube. The exposure
times f o r the TLD's were controlled and recorded.
The TLD 800's (Li2Br407:Mn) were calibrated by placing TLD packets
i n the l u c i t e rod a t positions t h a t correspond t o the positions of
the N8S traceable ion chamber c a l i b r a t i o n s . A series of TLD
exposures f o r varying times provided data t o determine the TLD
response versus exposur data. These data were then f i t using the
power function X=(y/a)lBb where x = exposure, l O ' + R , and y = TLD
response. The resulting formula was used t o calculate the c a l i -
brated R/h from TLD response data i n a l l the 6oCo exposure tubes a t
the 3730 f a c i l i t y . The calibrated exposure r a t e s f o r the 6oCo
exposure tubes a t the 3730 f a c i l i t y a r e presented i n Table 2
RPP-7806 Rev. 0 5-G
PNL TABLE 1. Ion Chamber Calibration, 8/24/84, TUBE 21
POSITION
(INCHES
FROM
BOlTOM) CALIBRATED
FLUX: lo5 R l h
6 4.76
8 5.06
10 5.16
RPP-7806 Rev. 0 6-G
PNL TABLE 2. Calibrated Exposure Rates
3730 6oCo FACILITY, 8/24/84.
POSITION
(INCHES TUBE TUBE TUBE TUBE TUBE TUBE
FROM
BOTTOM) -11 12 13 14 15 16
FLUX: lo6 R/h lo5 R/h R/h
I@ 0
1 5 R/h 0
1 4 R/h 104 R/h
1 0.862 2.50 2.22 1.50 8.83 2.07
3 1.28 3.51 2.79 1.59 8.86 5.78
5 2.32 4.83 3.42 1.56 8.99 6.44
7 3.97 7.44 4.21 1.67 9.35 6.48
9 5.78 9.37 4.58 1.64 9.73 6.77
11 63
.3 10.7 5.01 1.61 9.65 6.67
13 6.47 11.0 5.06 1.51 9.29 6.63
15 6.01 10.7 4.72 1.38 9.37 6.91
17 5.18 9.00 4.49 1.28 9.17 6.71
19 3.37 6.79 3.52 1.17 8.69 6.51
21 1.79 4.94 3.02 1.04 7.94 6.26
23 0.93 3.16 2.43 0.70 7.66 6.12
25 0.53 2.33 1.83 0.48 7.05 6.17
27 0.33 1.57 1.42 0.32 3.00 4.55
29 0.18 1.04 1.04 0.24 1.83 2.13
31 0.12 0.69 0.67 0.17 1.35 1.15
POSITION
(INCHES TUBE TUBE TUBE TUBE TUBE TUBE
FROM
BOlTOMl
- - - -
17 18 19 #I0
-
111 #12
FLUX: l@R/h 14 R l h
0 104 R/h 104 R / h lo5 Rlh lo5 R l h
1 5.16 1.26 1.01 0.22 3.01 2.82
3 5.77 3.21 3.16 0.50 3.70 4.09 -
5 5.72 4.05 3.57 1.46 4.39 5.34
7 5.82 4.23 3.62 2.36 4.79 6.63
9 5.74 4.22 3.58 2.92 5.45 7.94
11 5.56 4.18 3.82 3.12 5.53 8.30
13 5.65 4.49 3.66 3.06 4.94 8.41
15 5.40 4.58 3.62 3.16 4.07 7.12
17 5.23 4.47 3.66 3.08 3.55 6.42
19 5.09 4.41 3.62 3.07 2.84 4.89
21 4.68 4.05 3.50 2.99 2.16 3.38
23 2.36 4.24 3.59 3.02 1.61 2.42
25 1.36 3.92 3.46 3.09 1.08 1.66
27 0.86 2.89 2.19 2.98 0.76 1.02
29 0.59 1.34 0.97 2.90 0.50 0.73
31 0.50 0.91 0.58 1.59 0.35 0.54
RPP-7806 Rev. 0 7-G
page 5 of 9
PNL TABLE 2. Calibrated Exposure Rates (Continued)
3730 6oCo FACILITY, 8/24/84.
POSITION
(INCHES TUBE TUBE TUBE TUBE TUBE TUBE
FROM 113 114 115 115A 115B 116
BOlTOMI
FLUX: 105 R l h
- 105 R l h lo5 R / h
- - - lo4 Rlh 105 R l h
lo5 R l h
- -
1 3.30 3.16 1.73 1.03 1.96 5.12
3 4.59 3.97 2.18 1.26 2.26 7.93
5 6.26 4.73 2.67 , 1.39 2.70 11.4
7 7.15 5.66 3.03 1.52 2.90 13.1
9 8.02 6.02 3.10 1.55 2.96 14.6
11 8.28 5.79 3.11 1.67 2.95 14.6
13 8.02 5.53 3.06 1.59 2.84 14.6
15 6.99 4.79 2.82 1.45 2.70 13.2
17 5.74 3.93 2.63 1.36 2.51 11.4
19 4.35 3.29 2.18 1.16 2.18 8.38
21 3.07 2.59 1.79 1.03 1.93 4.95
23 2.54 1.87 1.46 0.85 1.61 2.93
25 1.61 1.38 1.13 0.68 1.33 1.69
27 1.07 0.90 0.77 0.52 1.07 1.10
29 0.76 0.61 0.57 0.41 0.84 0.65
31 0.53 0.50 0.40 0.32 0.70 0.47
POSITION
(INCHES TUBE TUBE TUBE TUBE TUBE TUBE
FROM 117 $18 $19 120 121' 1212
BOTTOM)
- - - -
lo5 R l h
FLUX: 105 R l h IO5 R l h lo5 R/h
- 105 R l h
lo5 R/h
1 1.83 1.45 1.43 1.55 1.81 2.14
3 2.40 2.09 2.07 2.29 3.16 3.34
5 2.86 2.50 2.77 3.05 4.36 4.28 -
7 3.40 3.19 3.39 3.54 5.05 5.03
9 3.37 3.44 3.62 3.78 5.38 5.52
11 3.29 3.39 3.73 3.87 5.28 5.67
13 3.19 3.48 3.50 3.69 5.17 5.52
15 2.76 3.28 3.15 3.43 4.40 4.72
17 2.30 2.69 2.77 2.72 3.95 4.14
19 1.62 1.99 2.11 2.07 2.70 2.84
21 1.11 1.31 1.41 1.32 1.62 1.74
23 0.67 0.84 0.82 0.78 0.94 1.05
25 0.44 0.55 0.49 0.49 0.57 0.64
27 0.30 0.36 0.33 0.34 0.37 0.43
29 0.21 0.26 0.23 0.23 0.26 0.31
31 0.16 0.18 0.18 0.17 0.18 0.22
RPP-7806 Rev. 0 8-G
1 - WITH AUTOCLAVE IN TUBE 116
2 ~ W I T H O U T AUTOCLAVE IN TUBE 116
PNL TABLE 2. Calibrated Exposure Rates (Continued)
3730 6oCo FACILITY, 8/24/84.
POSITION
(INCHES TUBE TUBE TUBE TUBE TUBE TUBE
FROM
BOITOM)
122 X23A 124A
- - 125A
--
126A 127A
1
FLUX: 0
15 R/h
1.86
lo4 R / h
1.92
l o 4 R/h
- 104 R/h - 103
104 R/h
0.96
Rlh
5.15
2.24 1.72
3 2.74 2.39 2.70 1.96 1.14 6.66
5 3.71 3.05 3.46 2.53 1.46 7.43
7 4.11 3.28 3.97 2.96 1.61 9.23
9 4.78 3.59 4.05 3.08 1.67 9.36
11 4.85 3.90 4.27 3.34 1.74 9.67
13 4.82 3.71 4.24 3.07 1.76 9.25
15 4.42 3.69 4.01 2.97 1.n 9.53
17 3.68 3.45 3.68 2.76 1.53 8.44
19 2.68 2.90 3.13 2.43 1.46 7.82
21 1.70 2.46 2.54 2.09 1.24 6.94
23 0.99 1.94 1.94 1.61 1.03 5.84
25 0.58 1.36 1.40 1.19 0.81 4.64
27 0.38 1.04 1.06 0.83 0.61 3.65
29 0.24 0.78 0.80 0.65 0.45 2.81
31 0.19 0.66 0.61 0.49 0.33 2.29
POSITION
(INCHES TUBE TUBE TUBE TUBE TUBE TUBE
FROM X28A Y29A 130A 131A 132A 133A
BOlTOM)
FLUX: 13 R/h
0 lo3 R / h 13 Rlh
0 12Rlh
0 Id: R / h lo3 R/h
1 2.55 1.54 0.74 4.36 3.40 2.39
3 3.17 1.n 0.85 4.64 4.23 3.22 -
5 3.79 2.13 1.05 6.46 5.94 3.44
7 3.95 2.41 1.11 6.77 7.50 3.84
9 4.24 2.34 1.17 7.97 8.91 3.89
11 4.74 2.51 1.29 8.50 9.19 4.03
13 4.65 2.43 1.24 8.89 9.98 4.11
15 4.46 2.39 1.21 8.71 10.50 4.09
17 4.28 2.36 1.20 8.53 9.80 4.20
19 3.79 2.24 1.17 8.82 10.60 4.18
21 3.38 1.91 1.08 8.45 10.60 4.06
23 3.04 1.76 0.98 7.74 10.10 3.61
25 2.64 1.51 0.90 6.81 9.38 2.73
27 2.20 1.31 0.81 6.48 9.03 2.06
29 1.76 1.14 0.74 5.49 7.73 1.64
31 1.46 0.93 0.60 5.36 6.26 1.22
RPP-7806 Rev. 0 9-G
G. L. Jones
December 5, 1984
Page 7
Sources of error t h a t exist in the 3730 6oCo f a c i l i t y include
source decay and exposure geometry. No source decay was a p p l i e d t o
TLD data d u r i n g the month of TLD exposures following the traceable
ion chamber calibration of Tube 21. The ion chamber calibration
made on 8/24/84 i s the o f f i c i a l data of calibration for a l l tubes.
The exposure r a t e a t the f a c i l i t y a l s o changes w i t h geometry caused
radiation scatter and attenuation. The calibration of Tube 2 1 was
effected by the presence of a dense object i n Tube 16. Dense
objects were a l s o present i n Tubes 5, 7, and 28A during the Cali-
bration (see exposure tube map). A graph of the Tube 2 1 exposure
r a t e s w i t h and w i t h o u t the dense object i n Tube 16 i s presented.
Sources of e r r o r f o r this calibration include: exposure geometry,
ion chamber measurement error, TLD response e r r o r , calibration
curve f i t error, and source decay e r r o r . The estimated uncertainty
associated w i t h the TLD readings a t each position i s 10%. The
overall average tube calibration uncertainty i s estimated t o be 6%
(near the maximum). This calibration i s recorded in long BNW
50560.
RPP-7806 Rev. 0 10-G
page9 of 9
TUBE 21
7.0
6 .O
5.0
4.0
3.0
2.0
1.0
0.0
0 4 12 16 20 24 28 32
INCHES FROM BOTTOM
RPP-7806 Rev. 0 11-G
Gamma Irradiation Instrument
RF'P-7806 Rev. 0 12-G
Gamma Irradiation Instrument
RPP-7806Rev. 0 13-G
APPENDIX H
Technical
References
RPP-7806 Rev. 0 1-H
EnviroChem Technologies, SpeciJicationData Sheet, Envirolastic AR 425, 9/26/2000.
Paul Klieger and Joseph E. Lamond, Signijcance o Tests and Properties of Concrete and
f
Concrete-Making Materials, ASTM STP 169C 1994 pg. 133.
Paul Klieger and Joseph E. Lamond, Signijcance o Tests and Properties ofconcrete and
f
Concrete-Making Materials, ASTM STP 169C 1994 pg. 528.
RF’P-7806 Rev. 0 2-H
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