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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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                    -7806 Rev. 0                                                                                                                               3-E
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  5 ," 2 RPP-7806 Rev. 0                                                                                   4-E
                  __    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
..
I..
 _.   ..   . . _ ~.- ....
                   _        ,-

				
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