DRC-2013-003081 - 0901a068803b5076

Energy Fuels Resources (USA) Inc
225 Union Blvd. Suite 600
"DRC-2013-003081 toke^d^fiin
ENERGYFUELS wwwww i 3039742140
wv\rw.energyfuels com
VIA OVERNIGHT DELIVERY
August 30, 2013
Mr. Rusty Lundberg
Director of the Utah Division of Radiation Control
State of Utah Department of Environmental Quality
195 North 1950 West
P.O. Box 144850
Salt Lake City, UT 84116-4850
Re: White Mesa Uranium Mill - RML UT1900479
December 15,2011 Request to Amend Radioactive Materials License to Allow
Processing of Alternate Feed Materials from Sequoyah Fuels Corporation
Response to December 4,2012 Utah Division of Radiation Control Request for
Information
Dear Mr. Lundberg:
This letter responds to the Division of Radiation Control's ("DRC's") Request for Information ("RFI")
email dated June 11, 2012 and letter dated December 4, 2012 regarding Energy Fuels Resources (USA)
Inc.'s. ("EFRI's") December 15, 2011 Request to Amend (the "December 2011 Amendment Request")
the White Mesa Mill's (the "Mill's") Radioactive Materials License UT1900479 (the "RML" or the
"License") to allow processing of alternate feed material from Sequoyah Fuels Corporation (the
"Uranium Material"). For ease of review, each of DRC's comments is provided verbatim below in
italics, followed by EFRI's response.
A "redline" Revision of the Amendment Request is attached as Appendix A to this letter. Upon
approval of the Amendment Request, a final "clean" version of the Amendment Request will be
submitted.
June 11,2012 Comments
Comment 1
DUSA should explain what the analytical data provided in the Outreach Laboratory analytical report
dated March 13, ,2006 represent (on pages 72-75 of the pdf document entitled "SEQUOYAH
FUELS CORP Final OCR reducedpdf). Radionuclide isotopic and total uranium analytical results are
presented for 8 solid samples. However, it is not clear from the lab report, and is hot explained
anywhere in Lie. Amendment application where these samples were collected or what the samples
represent (e.g., are these additional dewatered raffinate sludge samples from the initial dewatering
test?). It is also not clear whether the analytical results for these samples are reported on a wet weight
NAWMMVAlternate Feeds\Sequoyah Fuels\7.15.13 response to DRC comments\Documents for Final\Final response to
DRC comments SFC 8.30.13.doc
elNERGYFUELS
VIA OVERNIGHT DELIVERY
August 30, 2013
Mr. Rusty Lundberg
Director of the Utah Division of Radiation Control
State of Utah Department of Environmental Quality
195 North 1950 West
P.O. Box 144850
Salt Lake City, UT 84116-4850
Re: White Mesa Uranium Mill-RML UT1900479
Energy Fuels Resources (USA) Inc.
225 Union Blvd. Suite 600
Lakewood, CO, US, 80228
3039742140
www.energyfuels.com
December 15, 2011 Request to Amend Radioactive Materials License to Allow
Processing of Alternate Feed Materials from Sequoyah Fuels Corporation
Response to December 4, 2012 Utah Division of Radiation Control Request for
Information
Dear Mr. Lundberg:
This letter responds to the Division of Radiation Control's ("DRC's") Request for Information ("RFI")
email dated June 11, 2012 and letter dated December 4, 2012 regarding Energy Fuels Resources (USA)
Inc.'s. ("EFRI's") December 15, 2011 Request to Amend (the "December 2011 Amendment Request")
the White Mesa Mill's (the "Mill's") Radioactive Materials License UT1900479 (the "RML" or the
"License") to allow processing of alternate feed material from Sequoyah Fuels Corporation (the
"Uranium Material"). For ease of review, each of DRC's comments is provided verbatim below in
italics, followed by EFRI's response.
A "redline" Revision of the Amendment Request is attached as Appendix A to this letter. Upon
approval of the Amendment Request, a final "clean" version of the Amendment Request will be
submitted.
June 11, 2012 Comments
Comment 1
DUSA should explain what the analytical data provided in the Outreach Laboratory analytical report
dated March 13, 2006 represent (on pages 72-75 of the pdf document entitled "SEQUOYAH
FUELS CORP Final OCR reduced. pdF). Radionuclide isotopic and total uranium analytical results are
presented for 8 solid samples. However, it is not clear from the lab report, and is not explained
anywhere in Lic. Amendment application where these samples were collected or what the samples
represent (e.g., are these additional dewatered raffinate sludge samples from the initial dewatering
test?). It is also not clear whether the analytical results for these samples are reported on a wet weight
N:\WMM\Aiternate Feeds\Sequoyah Fuels\7.15.13 response to DRC comments\Documents for Final\Final response to
DRC comments SFC 8.30.13.doc
Letter to Rusty Lundberg
August 30, 2013
Page 2 of 47
basis or on a dry weight basis. The suite of samples tested has sample designation SF05-338 (corrected
designation from previous designation SF05-234)
EFRI response to Comment 1
The Outreach Analytical Laboratory data package, dated March 13, 2006, contains the data for 8
dewatered raffinate sludge samples. Each of the 8 samples is a composite sample of the dewatered
raffinate sludge. The composites were made by collecting a grab sample of raffinate sludge from each
bag of dewatered raffinate sludge during the dewatering process. The grab samples from each cell (A
through H) were composited to form a representative sample of the dewatered raffinate sludge from that
cell. All analyses are reported on a dry-weight basis. The data in Attachment D.lcv of the Revised
August 2013 Amendment Request which is included as Appendix A to this letter have been annotated to
reflect the cell from which the composite originated.
Comment 2
In Table 1 of Attachment 2, and in column 1 of Table 4 in Attachment 5 of the Lic. Amendment
application, please clarify whether the analytical results for the dewatered sludge samples (SF03-278)
are reported on a wet weight basis or on a dry weight basis.
EFRI response to Comment 1
The analytical results are reported on a dry weight basis.
Comment 3
In column 1 in Table 1 of Attachment 2 of the Lic. Amendment application, please clarify whether the
analytical results for the raw sludge samples (ave. of results of the four samples SDOO 1 thru SD004) are
reported on a wet weight basis or on a dry weight basis.
The analytical results are on a dry weight basis; however, those results have been deleted from the
Revised August 2013 Amendment Request.
EFRI Response to Comment 3
Comment 4
In Table 4 of Attachment 5 of the Lic. Amendment application, the explanation for footnote 12 is
missing.
EFRI Response to Comment 4
The explanation for footnote 12 has been added to Table 4 of Attachment 5.
Letter to Rusty Lundberg
August 30, 2013
Page 3 of 47
GENERAL COMMENTS
General Comment 1
Specific comments stated below address the Applicant's repeated statements that the Uranium Material
proposed to be processed in the White Mesa Mill has characteristics that are within the envelope of
material characteristics previously authorized to be processed at the Mill.
a. Once the specific comments stated below have been addressed, please review and evaluate the
correctness of conclusions stated throughout the text of the amendment application that
"previously accepted or authorized analyses, plans, programs, procedures, practices,
equipment, etc. need not be extended or revised. Justify each new conclusion. To the extent
necessary, extend or revise previously accepted or authorized analyses, plans, programs,
procedures, practices, equipment, etc. and submit them for the Division's consideration and
approval.
EFRI Response to General Comment la
EFRI has reviewed the data provided in the December 2011 Amendment Request and supplemental data
provided in the Revised August 2013 Amendment Request. Based on this review, EFRI maintains that
the Uranium Material does not pose substantially different or greater hazards than other feed materials
already approved, and in most instances poses significantly less hazards than other materials handled
safel y at the Mill, for the reasons discussed below.
All data and additional evaluations continue to indicate that the Uranium Material is comparable to or
similar in chemical and radiological composition to many previously approved alternate feed materials
that the Mill has processed, as described in the December 201 i Amendment Request. All the
constituents in the Uranium Material have either been reported to be, or can be assumed to be, already
present in the Mill's tailings system or were reported in other licensed alternate feed materials, at levels
comparable to or higher than those reported in the Uranium Material. The focus of the analysis in both
the December 2011 Amendment Request and the Revised August 2013 Amendment Request is on any
difference that may necessitate changes to the existing approved programs. The storage and processing
of the Uranium Material will not introduce new constituents or new constituent forms (dissolved,
particulate or gaseous) or create significantly new human or environmental exposure risks that have not
already been addressed by previous submittals and approvals by appropriate authorities (US Nuclear
Regulatory Commission ("NRC") or DRC).
Based on this review, and because the Uranium Material does not pose substantially different or greater
hazards than other feed materials already approved, as addressed in the application and the enclosed
responses to these comments, EFRI maintains that the Mill can safely handle the Uranium Material in
accordance with existing Mill controls and standard operating procedures ("SOPs"). Additionally, EFRI
maintains that the existing monitoring programs are adequate, and no new monitoring procedures are
required.
Letter to Rusty Lundberg
August 30, 2013
Page 4 of 47
General Comment 1 b, Continued
b. Previously accepted or authorized analyses, plans, programs, procedures, practices, equipment,
etc. include (but are not necessarily limited to) the following:
• H ••• there will be no incremental public health, safety or environmental impacts over and above
previously licensed activities" stated on Page 9 of the Amendment Request.
EFRI Response
Please review the responses to comments listed below. The discussions, data and calculations in the
December 2011 Amendment Request, the Revised August 2013 Amendment Request, and the responses
to these comments demonstrate that:
./ No new hazardous constituents will be introduced to the Mill, the tailings system, groundwater
or air (RMPR, responses to General Comments 1a and 1b, and the responses to Specific
Comments 3a through 3e),
./ There will be no additional environmental or worker safety impacts due to increased levels of
constituents previously introduced into the Mill (response to Specific Comments 3a through 3e
and the responses to General Comment Ib). Specifically, the Revised August 2013 Amendment
Application has been modified by incorporation of the Mill's Standard Operating Procedure
("SOP") to address potentially elevated thorium levels, tailored to the specific radiological
characteristics of the Uranium Material. As a result, there will be no additional worker safety or
environmental impacts from receipt, storage on the ore pad, processing or disposal in tailings due
to potentially elevated levels of radionuclides relative to other previously licensed alternate feed .
./ There will be no additional transportation impacts (response to General Comment 1 b)
./ The Uranium Material:
o Produces no additional impacts to surface water (response to remainder of General
Comment 1 b below)
o Produces no additional impacts to groundwater (response to remainder of General
Comment Ib below)
o Produces no additional risks to air (response to remainder of General Comment Ib
below)
o Produces no increased radiation hazard (response to remainder of General Comment 1 b
below)
o Produces no impacts or changes to Decontamination and Decommissioning, or to
Reclamation (response to remainder of General Comment 1 b below)
Therefore, based on review of the December 2011 Amendment Request and supplemental information
in this letter, and the Revised August 2013 Amendment Request, EFRI maintains that the statements in
the December 2011 Amendment Request, that there will be no incremental public health, safety or
environmental impacts over and above previously licensed activities is justified.
Letter to Rusty Lundberg
August 30, 2013
Page 5 of 47
General Comment Ib, Continued
• " ... there are no anticipated impacts to the environment ... above those already anticipated in the
existing environmental statements and environmental assessments associated with the ·Mill's
approved license ... "stated on Pages 9 and 13 of the Amendment Request ..
EFRI Response
Please see response to general Comment 1 b, first bullet, above.
General Comment Ib, Continued
• " ... there will be no significant incremental radiological impacts associated with transportation
of Uranium Material to the Mill, over and above other previously licensed ores and alternate
feed materials at the Mill" stated on Page 11 of the Amendment Request.
EFRI Response
The transportation considerations assessed for shipping the Uranium Material are presented in Section
4.2 of the December 2011 Amendment Request. Two aspects of transportation are considered,
radiological matters and traffic matters. As stated in Section 4.2.1 of the application, the estimated
range of truck shipments would be from 555 to 835 trucks over a period of 22 to 33 weeks. This
equates to a maximum of 25 trucks in any given week on average.
Section 4.2.2.a) of the December 2011 Amendment Request addresses radiological considerations.
Specifically, the application states the following.
"The transport of radioactive materials is subject to limits on radiation dose rate
measured at the transport vehicle as specified in the US Code of Federal Regulations.
The external radiation standards for these shipments are specified in 10 CFR 71.47
sections (2) and (3) as less than 200 millirems per hour ("mremlhr") at any point on the
outer suiface of the vehicle, and less than 10 mremlhr at any point two meters from the
outer lateral suifaces of the vehicle. All exclusive use trailer trucks will be scanned by
SFC prior to departure from the Gore facility to ensure that these limits are satisfied."
In addition, the application has been modified to clarify that:
"All applicable requirements of 49 CFR Part 172 and Part 173 will be met, and the
selected transport company will have all the required training and emergency response
programs and certifications in place. "
Therefore, shipment of the Uranium Material will comply with all applicable federal safety standards for
transportation of Class 7 radiological materials. As such, EFRI re-asserts that the transportation of the
Letter to Rusty Lundberg
August 30, 2013
Page 6 of 47
Uranium Material by truck from the Gore facility to the Mill will have no significant transportation
related radiological impacts.
The Uranium Material will travel through Utah most likely via Utah State Highway ("SH") 262 to SH
191 and north on SH 191 to the Mill. Section 4.2.2.b.ii of the December 2011 Amendment Request
addresses traffic impacts for this route. The original 1979 Final Environmental Statement (FES) and
1978 Environmental Report contemplated the transportation impacts associated with approximately 68
round trips on local highways by 30-ton ore trucks to the Mill per day. In addition, the FES
contemplated approximately 183-275 truck shipments of yellowcake from the Mill per year, which
equates to one truck everyone to two days based on a seven day work week (one truck every day or so,
based on a five-day work week).
Sections 4.2.2b.ii and 4.2.2b.iii of the December 2011 Amendment Request assesses the current truck
traffic on SH 262 and SH 191 which are the principal Utah roadways on which trucks carrying the
Uranium Material would reach the Mill. These sections identify that, based on 2009 data from the Utah
Department of Transportation ("UDOT"), an average of 25 additional trucks per week (5 trucks per day)
traveling this route to the Mill represents an increased traffic load of less than two percent (2%) for a
finite period of 22 to 33 weeks.
This level of truck transportation volume is well below the level contemplated in the original FES and
represents a minute fraction of the existing truck volume on the transportation route. Therefore, EFRI
re-asserts that transportation impacts associated with the movement of the Uranium Material by truck
from the Gore facility to the Mill are not expected to be significant.
General Comment 1 b, Continued
• "Existing accident response and spill response procedures are therefore sufficient for
management of potential transportation accidents or spills of the Uranium Material." stated on
Page 12 of the Amendment Request.
EFRI Response
The Mill's Emergency Response Plan addresses transportation accidents and spills involving natural
ores, alternate feeds, and yellowcake. The U.S. Department of Transportation ("DOT") requires that
EFRI maintain personnel trained in transportation emergency and spill response. As discussed in the
response to General Comments 1a and 1b, and the responses to Specific Comments 3a through 3e,
below, the Uranium Material does not contain any chemical constituents that have not already been
transported to the Mill at comparable or higher concentrations. As discussed in the response to 1 b
above, the Revised August 2013 Amendment Request has been modified by incorporation of the
Mill's SOP for potentially elevated thorium levels, tailored to the specific radiological characteristics
of the Uranium Material, to assure there are no additional effects to worker safety or the environment.
Section 4.2.2 of the December 2011 Amendment Request has been modified as shown in Section 4.2.2
of the Revised August 2013 Amendment Request, to clarify that all applicable requirements of 49
CFR Parts 172 and 173 will be met and the selected transport company will have all the required
training and emergency response programs and certifications in place. Therefore, EFRI maintains that
Letter to Rusty Lundberg
August 30, 2013
Page 7 of 47
the existing accident response and spill response procedures are sufficient for management of
transportation of the Uranium Material.
General Comment Ib, Continued
• "... the Uranium Material poses no additional hazards during transport above previously
licensed activities" stated on Page 12 of the Amendment Request.
EFRI Response
The response to General Comment 1 b, bullets three and four, above, address radiological and traffic
volume impacts of transportation of the Uranium Material. The response to General Comments la and
1b, and the responses to Specific Comments 3a through 3e, below, demonstrate that the Uranium
Material does not contain any chemical constituents that have not already been transported to the Mill at
comparable or higher concentrations. As discussed in the response to 1 b above, the Revised August
2013 Amendment Request has been modified by incorporation of the Mill's SOP for potentially elevated
thorium levels, tailored to the specific radiological characteristics of the Uranium Material, to assure
there are no additional effects to worker safety or the environment.
Therefore, EFRI maintains that the Uranium Material poses no additional hazards during transport above
previously licensed activities.
General Comment Ib, Continued
• " ... the receipt and processing of Uranium Material at the Mill will not have any incremental
impacts on groundwater over and above existing licensed operations" stated on Page 16 of the
Amendment Request.
EFRI Response
The primary potential pathway at the Mill for effects to groundwater is the potential leakage of a cell
liner.
The December 2011 Amendment Request and the Revised August 2013 Amendment Request provide
composition data for the Uranium Material in the RMPR in Attachment 2. As indicated in the RMPR
and discussed in Attachment 5 to the application, the Uranium Material does not contain any chemical
or radiological constituents that have not previously been licensed for receipt and management at the
Mill, in conventional ores or other alternate feed materials licensed for processing, at levels equivalent
to or higher than those in the Uranium Material.
Specific constituents in the Uranium Material that are present at levels higher than those of conventional
ores, but within those of previously licensed alternate feed materials, were addressed in responses to
Specific Comments 3e and 3j, below.
Letter to Rusty Lundberg
August 30, 2013
Page 8 of 47
The response to Specific Comment 3e demonstrates that while arsenic ("As"), lead ("Pb"), barium
("Ba"), and beryllium ("Be"), are present at levels above those in Colorado Plateau ores, their levels in
the Uranium Material are well within the levels of these metals in other alternate feed materials
previously processed. Table 4 of Attachment 5 to both the December 2011 Amendment Request and
the Revised August 2013 Amendment Request demonstrate that the levels of these constituents in the
Uranium Material will produce a minimal to moderate change in the resulting concentrations in tailings
following the processing of the material, and therefore no significant change in the effects to
groundwater from potential leakage from tailings system.
As, Pb and Be are currently monitored in groundwater under the requirements of the Mill's Groundwater
Discharge Permit ("GWDP"). The response to Specific Comment 3j addresses why, based on the
respective KDs for calcium ("Ca") and Ba, monitoring for Ca provides a representative and conservative
indicator of the behavior of Ba in groundwater. Further, the Mill monitors for a number of other
dissolved constituents, such as chloride, fluoride, and sulfate, each of which is an anion that is expected
to have a higher mobility in groundwater than a cation such as Ba. These anions can be used as
indicators of potential tailings cell seepage, and because of their mobility, as 'early warning' indicators
for less mobile constituents such as Ba. Chloride in particular is a conservative solute that is not retarded
with respect to groundwater flow. As discussed in Davis and DeWiest (1966) "All chloride salts are
highly soluble, so chloride is rarely removed from water by precipitation except under the influence of
freezing or evaporation. Chloride is also relatively free from effects of exchange, adsorption, and
biological activity. Thus, if water once takes chloride into solution, it is difficult to remove the chloride
through natural processes." That is, the Mill's monitoring for chloride provides a more effective early
warning of potential tailings cell liner leakage than would be achieved by monitoring of any constituent
in the Uranium Material.
As a result of these considerations, EFRI maintains that the Uranium material will not produce any
incremental increase in effects to groundwater.
General Comment 1 b, Continued
• " ... there will be no incremental [suiface water] impacts over and above previously licensed
activities" stated on Page 17 of the Amendment Request
EFRI Response
Attachment 2 to the December 2011 Amendment Request provided a completed RMPR for the Uranium
Material. Table 4 of Attachment 5 to the December 2011 Amendment Request presented a comparison
of constituent concentrations in existing ores and other alternate feed materials processed at the Mill as
well as the range of constituent concentrations in the Uranium Material.
Table 4 of Attachment 5 has been modified and clarified, and a revised version of this table is provided
in the Revised August 2013 Amendment Request, which is included as Appendix A to this letter. These
data indicate that the Uranium Material constituents are present in concentrations within the range of
ores and other alternate feed materials which are already permitted to be processed at the Mill under the
existing license.
Letter to Rusty Lundberg
August 30, 2013
Page 9 of 47
The modes of potential impact to surface waters from Uranium Material delivery, storage, processing
and long-term disposal are from, 1) release of site surface runoff containing Uranium Material
contaminants, 2) discharge of other process liquid effluents containing Uranium Material contaminants
to surface water systems, andlor 3) airborne transport of Uranium Material particulates related to
delivery, storage and processing of these materials. As stated in Section 4.7 of the December 2011
Amendment Request, protection of surface water from potential impacts related to receiving, storing,
and processing this Uranium Material will be accomplished through control of potential surface water
discharges using the Mill's existing storm water and liquid effluent controls. Specifically, storm water
runoff from the Mill and facilities, including the ore storage area where the Uranium Material will be
received and stored, is directed to the tailings impoundments through approved storm water controls
contained in the Stormwater Best Management Practices Plan for White Mesa Mill (EFRI, September
2012). These are the same controls used for storage of all other alternate feed materials. Since the
Uranium Material will not provide substantially different input to the ore storage area storm water than
is already contributed from conventional ores and other approved alternate feed materials, there is no
reasonable mechanism for new or incremental risk of discharge to surface waters resulting from the
receipt and processing of Uranium Material at the Mill or the disposition of the resulting tailings.
In addition, all other Mill process liquid effluents, laundry, and analytical laboratory liquid wastes that
could carry potential Uranium Material contaminants will be discharged to the Mill's tailings
impoundments for disposal using the existing appropriate and approved management systems as per
Condition 10.2 of the RML. Further, control of potential air transport of Uranium Material particulates
from storage and handling will be performed using standard approved dust control and worker protective
equipment practices (see the December 2011 Amendment Request Section 4.10.2.d).
At the current time, Part II.BA.h of the State of Utah Air Approval Order ("AO") contemplates that the
moisture content of materials handled by front-end loading operations and truck-dumping operations are
not less than 4% by weight during these operations. The Uranium Material will have a moisture content
of approximately 22 to 77 percent (as noted in Attachment 2 of the December 2011), which is 5.5 to 19
times greater than the minimum moisture content currently contemplated for ores and feeds stored on
the ore pad by the Mill's AO for minimization of the potential dust generation. Given the factors above,
EFRI maintains that wind transport of Uranium Material particulates have no new or incremental risk of
constituent discharge or potential adverse impact to surface waters.
Therefore, EFRI has demonstrated and maintains that 1) the Uranium Material does not contain
constituents outside the range of materials already licensed for processing at the Mill, 2) the Uranium
Material does not exhibit leaching characteristics that will allow a significant potential to release
constituents to site runoff (see response to Specific Comment 3f, below), 3) experience with outdoor
storage and management of the Uranium Material establishes a reasonable basis for concluding storage
on Mill site ore pads will not require special handling, 4) that there are appropriate approved
management systems for control site runoff and other liquid effluents to protect surface water resources,
and 5) the potentially elevated thorium levels will be mitigated through the implementation of an SOP.
• "The existing air particulate monitoring program is equipped to handle all such ores and
alternate feeds" stated on Page 17 of the Amendment Request.
Letter to Rusty Lundberg
August 30, 2013
Page 10 of 47
EFRI Response
As stated in the December 2011 Amendment Request, and due to moisture contents as high as 77
percent, the Uranium Material has little potential for generating dust and particulates. The Mill's AO
currently limits dust potential by requiring in Part II.B.Lc that dusts from the ore loading areas may not
exceed 15% opacity. At the current time, Part II.B.4.h of the AO contemplates that the moisture content
of materials handled by front-end loading operations and truck-dumping operations are not less than 4%
by weight during these operations.
As stated in Section 4.2.1 and 4.2.7 of the December 2011 Amendment Request, the Uranium Material
will be delivered in SuperSaks in exclusive use trucks with poly-lined bottoms and sides, or flatbed style
trailers with sidewalls and tarp covers, which will be unloaded onto the ore pad for temporary storage
pending processing as is currently done for conventional ores and some alternate feed materials. The
Uranium Material will be unloaded and stored in a manner essentially identical to conventional ore. In
addition, the Uranium Material will be relatively moist, with an average moisture content of
approximately 22 to 77%, and has been characterized (as noted in Attachment 2 of the December 2011
Amendment Request). As mentioned in the response to General Comment 1b, 6th bullet, above, this
moisture content surpasses the current moisture requirement for ores and feeds in the Mill's AO by a
factor of 5.5 to 19 times.
The existing environmental air monitoring system, required per License Condition 11.2 of the RML, and
summarized in Section 5.5 of the Mill's License Renewal Application (UMETCO 1991) has been
approved by the NRC and the State of Utah and meets the requirements identified in NRC regulatory
Guide 4.14 (NRC, 1980; Section 2).
The monitoring program referenced above includes high volume air sampling devices collecting
airborne radioparticulate data both upwind and downwind of the Mill. These environmental data are
composited regularly and analyzed quarterly, with results being reported semi-annually. These data are
assessed with respect to the 10 CFR 20, Appendix B, Table 2, Effluent Concentration Limits for
unrestricted areas, to ensure that site operational practices for controlling particulate radionuclides and
dust are protective of public health.
Similarly, the existing occupational health air monitoring program approved under License Condition
11.4 of the RML, and as described in the Technical Evaluation Report ("TER") for NRC License
Amendment 7 (US NRC August 1998), meets the requirements for monitoring particulate radionuclides
in uranium mills (NRC, 1979) and has been approved by DRC. The TER for the NRC License
Amendment 7 is included as Appendix C to this letter.
EFRI has assessed many factors in developing the December 2011 Amendment Request, including the
adequacy of the existing stack emissions monitoring, fugitive emissions (dust) monitoring, and
environmental air particulate monitoring program. Since the Uranium Material constituent
concentrations are within the range of those for other ores and alternate feed materials already processed
and/or licensed for processing at the Mill (see response to General Comment la and Ib above and the
responses to Specific Comments 3a through 3e below) and since, moisture contents are as high as 77
Letter to Rusty Lundberg
August 30, 2013
Page 11 of 47
percent, the Uranium Material has no propensity to generate abundant dust sized particles. Further, the
Revised August 2013 Amendment Request has been modified by the incorporation of an SOP to
minimize any effect from the potentially elevated thorium levels.
As discussed in the response to Specific Comment 3d, below, EFRI has previously developed a
specific SOP, approved by the US NRC, for receipt, unloading, stockpiling, processing and tailings
management for alternate feed materials with elevated levels of thorium. This procedure was
originally developed for the W.R. Grace alternate feed material, which had much higher concentration
of Th-230 and Th-232 than the Uranium Material. A modified version of this SOP was also
implemented for the Heritage alternate feed material. EFRI has prepared a specific version of this
SOP, with similar protective measures, suitable for the Uranium Material. The Uranium-Material SOP
and its protective measures are described in the response to Specific Comment 3d, and a copy of the
SOP is provided in Attachment 7 of the Revised August 2013 Amendment Request, which is included
as Appendix A to this letter.
General Comment Ib, Continued
• " ... the Uranium Material will therefore pose a comparable or lower gamma and radon hazard
as other ores and alternate feed materials that have already been processed or licensed for
processing at the Mill" stated on Page 17 of the Amendment Request.
EFRI Response
Attachment 2 of the December 2011 Amendment Request presents a complete Radioactive Materials
Profile Record ("RMPR") for the Uranium Material. Table 1, below, summarizes the ranges of
radionuclide activity concentrations of the Uranium Material as well as other alternate feed materials
already approved for processing, and successfully processed at the Mill. These data demonstrate that the
primary gamma emitting radionuclide content (uranium, thorium and radium) of the Uranium Material
are below the maximum of the range of relevant radionuclide activity concentrations of conventional
ores and already-approved alternate feed materials. Therefore, the gamma radiation and radon
emissions from this Uranium Material will be correspondingly less than other conventional ores and
alternate feed materials that have been processed or licensed for processing at the Mill. Consequently,
EFRI maintains that the above references statement is correct and that these data are sufficient to support
this assertion.
However, as discussed in the response to General Comment la, above, EFRI has prepared a specific
SOP for management of the elevated thorium levels present in the Uranium Material. The Uranium-
Material SOP and its protective measures are described in the response to Specific Comment 3d, and a
copy ofthe SOP is provided in Attachment 7 of the Revised August 2013 Amendment Request, which is
included as Appendix A to this letter.
Letter to Rusty Lundberg
August 30, 2013
Page 12 of 47
Table 1
Comparison of Radionuclide Activity Concentrations in
Proposed Uranium Material and Previous Alternate Feeds
Range of Uranium Previously Licensed Source for Alternate Feed
Material RadionucIide Alternate Feed Information
RadionucIide Activity Concentrationl RadionucIide Activity
(pCi/g dry)2 Concentrations3,4
(pCi/g dry)2
Ra-226 135 to 367 2,000 avg; 10,400 max W.R.Grace Application April 2000
Weighted average 236
Th-228 449 to 1,110 2,000 avg.; 3,222 max W.R.Grace Application April 2000
Weighted average 699
Th-230~ 43,900 to 74,400 75 .5 mg/kg (1,555,000 Nevada Test Site Cotter Concentrate
Weighted average 55,685 pCi/g) avg., 143 mg/kg
(2,330,000 pei/g) max .6
Application March 1997
Th-232 1,060 to 4,990 8,000 avg.; 31,500 max W.R.Grace Application April 2000
Weighted average 2,385 1,190 avg. Heritage RMPR, undatedll
Unat 7,080 mg/kg to 10, 100 mg/kg 686,000 mg/kg max Mill lab monthly assays Cameco
UF4
I Attachment 2 of the December 2011 Amendment Request (Radioactive Material Profile Record, and associated tables)
2 pCi/g unless otherwise noted
3 Selected concentrations for constituents found in characterization data for other alternate feed materials licensed for
processing at the Mill, for comparison purposes only.
4. Mined ores range from 0.1 % to higher than 1 %. Some Arizona strip ores have ranged as high as 2% U30 g (1.7% V-nat).
Abundance of uranium daughters can be estimated from the assumption that ores are in secular equilibrium.
5. Th-230 is not a contributor to gamma emissions but has been included here because it is considered in the generation of
DACs for each ore or alternate feed material.
6. Based on Th-230 conversion of 20,600 pCi/g per mg/kg.
7. Monthly average grade assays of Cameco UF4 have periodically been as high as 80.7% U30 g (68.6% U).
g. Heritage alternate feed material was stored on the ore pad in bulk and managed under a high thorium SOP.
General Comment Ib, Continued
• "Gamma exposure to workers will be managed in accordance with existing Mill standard
operating procedures" stated on Page 18 of the Amendment Request.
EFRI Response
As described in the response to General Comment 1b, in the bullet immediately above this response, the
radionuclide activity of the primary gamma emitting radionuclides are within the maximum range of
relevant radionuclide activity concentrations of already approved alternate feed materials. Therefore,
the potential gamma emissions and potential worker exposure to gamma radiation will be within the
range of those already approved for processing at the Mill. Consequently, EFRI maintains that the
existing standard operating procedures and controls are adequate to maintain all radiological exposures
to protective levels and levels that are as low as reasonably achievable ("ALARA").
Letter to Rusty Lundberg
August 30, 2013
Page 13 of 47
General Comment Ib, Continued
• "Radon exposures to workers will be managed in accordance with existing Mill standard
operating procedures" stated on Page 18 of the Amendment Request.
EFRI Response
Based on the information provided in Table 1, above, in which it is demonstrated that the Uranium,
Radium, and Thorium activity concentrations of the Uranium Material are below the maximum range of
previously approved conventional ores and alternate feed materials, the resulting radon levels are
expected to be within the range for which the existing approved controls and monitoring programs are
appropriate. Therefore, no change to the existing radon exposure controls or the radiological monitoring
program is necessary.
General Comment Ib, Continued
• "The Mill ... can safely handle the Uranium Material in accordance with existing Mill standard
operating procedures" stated on Page 18 of the Amendment Request.
EFRI Response
EFRI has reviewed the General Comments, the Specific Comments and all related responses included
herein. Based on this review and because the Uranium Material does not pose substantially different or
greater chemical or radiological hazards than conventional ores and other alternate feed materials
already approved, as addressed in the December 2011 Amendment Request and the enclosed responses
to these comments, EFRI maintains that the Mill can safely handle the Uranium Material in accordance
with existing Mill standard operating procedures. As mentioned above, the Mill will apply its SOP to
potentially elevated thorium levels, tailored to the specific radiological characteristics of the Uranium
Material.
General Comment Ib, Continued
• "Existing monitoring programs are therefore adequate and no new monitoring procedures are
required" stated on .Page 19 of the Amendment Request.
EFRI Response
EFRI has reviewed the General Comments, the Specific Comments and all related responses included
herein. Based on this review and because the Uranium Material does not pose substantially different or
greater hazards than conventional ores and other alternate feed materials already approved, as addressed
in the application and the enclosed responses to these comments, EFRI maintains that the existing
monitoring programs are adequate and no new monitoring procedures are required. As mentioned
above, the Mill will apply its SOP to potentially elevated thorium levels, tailored to the specific
radiological characteristics of the Uranium Material.
Letter to Rusty Lundberg
August 30,2013
Page 14 of 47
General Comment Ib, Continued
• " ... there will be no decommissioning, decontamination or reclamation impacts associated with
processing the Uranium Material, over and above previously licensed Mill operations" stated on
Page 19 of the Amendment Request.
EFRI Response
As discussed in detail in the Mill's approved Reclamation Plan, the components of the decontamination
and decommissioning phase and reclamation phase of Mill closure are:
• Demolition of buildings, structures, and facilities (including Cell 1)
• Decontamination to free release standards of any equipment to be released from the site
• Disposal of all demolished structures and equipment in the Mill's tailings cells
• Decontamination of environmental media (on site and off site soil) to levels committed in the
Reclamation Plan
• Restoration of any potential groundwater contamination to groundwater compliance limits or
approved Alternate Corrective Action Concentration Limits
The long term-impacts that an alternate feed material could potentially have on the decontamination and
decommissioning phase, reclamation phase, or post -reclamation conditions are:
• Increase in volume of material in the tailings cells
• Addition of a new contaminant that cannot be managed or contained by the existing tailings
reclamation design
• Increase in concentration of a contaminant to a level that cannot be managed or contained by the
existing tailings reclamation design
• Contamination of soils or sediments requiring management at reclamation
• Change in nature of groundwater conditions requiring restoration at reclamation, to meet
applicable groundwater quality standards.
As discussed in the December 2011 Amendment Request and in the specific responses below, the
Uranium Material will produce none of these impacts because:
• The Uranium Material will not increase the volume of tailings. As discussed in the December
2011 Amendment Request, the Uranium Material will produce no greater volume of tailings than
would be produced from processing the same volume of ore or producing the same volume of
yellowcake product. Processing of the Uranium Material does not require the use of any new or
modified equipment; hence no additional volume of demolition material would be added to
tailings.
• The Uranium Material does not contain any constituents that have not already been introduced to
the Mill's tailings system. The RMPR, analytical data, and technical memorandum in the
December 2011 Amendment Request demonstrate that the sampling and analytical data are
Letter to Rusty Lundberg
August 30, 2013
Page 15 of 47
representative of the Uranium Material, and the Uranium Material contains no new constituents.
Processing of the Uranium Material will not require the use of additional chemicals not already
in use at the Mill. Therefore processing of the Uranium Material will not introduce any new
chemical constituent that cannot be managed or contained by the existing tailings reclamation
design.
• Processing of the Uranium Material will not increase the concentration of any contaminant to a
level that cannot be managed or contained by the existing tailings reclamation design. All
constituents present in the Uranium Material have already been introduced into the Mill at levels
higher than the levels present in the Uranium Material. Anticipated increases in barium levels in
tailings will have no effect on the integrity of the tailings liner.
• As discussed in the responses to General Comment 1 b and Specific Comments 3a through 3e,
processing of the Uranium Material will produce no additional mechanism for, or significant
increase in, airborne deposition in soils or sediments.
• As discussed earlier in response to General Comment 1 b and as discussed in the response to
Specific Comment 3j, processing of the Uranium Material will produce no additional pathway
for, or increase in, any potential effects to groundwater. Specifically, each constituent in the
Uranium Material is either monitored under the Mill's approved GWDP, or represented by a
constituent monitored in the GWDP, and the monitoring program required by the GWDP meets
the requirements of NRC Reg. Guide 4.14 and Utah groundwater regulations. Hence, processing
of the Uranium Material will not potentially change the nature of groundwater conditions in a
way that requires additional groundwater restoration at or before reclamation.
References for General Comments la and Ib
Dames and Moore, 1978. Environmental Report White Mesa Uranium Project, San Juan
County, Utah.
Energy Fuels Resources (USA) Inc., 2012. Stormwater Best Management Practices Plan for
White Mesa Mill.
United States Nuclear Regulatory Commission (NRC), 1979. Final Environmental Statement
Related to Operation of White Mesa Uranium Project.
United States Environmental Protection Agency (EPA) Test Methods for Evaluating Solid
Waste, Physical/Chemical Methods, Method 1311, Revision 0, July 1992.
Utah Division of Air Quality 2011. Air Approval Order Number DAQE-ANOlI2050018-11
Letter to Rusty Lundberg
August 30, 2013
Page 16 of 47
General Comment 2
2. Several internal references appear, on the basis of pages presented in the amendment request, to be
incorrect, either because the respective title pages are missing or the referenced material was not
submitted. Such is the case with internal references to Attachment D 1 Table I, Attachment D 1 Cii,
Attachment D 1 ciii, Attachment D I civ, and Attachment E4a.
Please correct these internal referencing problems in the revised amendment request and submit
currently missing referenced attachments (if any).
EFRI Response to General Comment 2
The internal references have been corrected. The Revised August 2013 Amendment Request in redline
format has been provided in Appendix A to this letter.
3. SPECIFIC COMMENTS
Specific Comment 3a
Reference Section 4.3 of the December 15,2011 Application for Amendment to Authorize Processing of
Sequoyah Fuels Corporation Alternate Feed Material (Amendment Request).
Please define the range of time over which delivered Uranium Material might remain in storage at the
Mill within the SuperSaks. State how the integrity of the SuperSaks might degrade over the time in
storage and the increased potential for radioactive releases with time. Estimate potential exposure of
workers and the environment due to the Uranium Material storage and from potential radioactive
releases from the storage area resulting from potential loss of integrity of the Supersaks.
EFRI Response to Specific Comment 3a
The uranium Material has significant economic value to both EFRI and SFC, hence the schedule for its
processing will be prioritized. In any case, it is expected that the Uranium Material would be processed
within a two-year period from receipt of the final shipments.
Based upon experience with receipt of other alternate feeds in SuperSaks and bulk bags, the Mill expects
that the flatbed trailers or lined end-dump trucks would be unloaded by tipping and dumping. A small
number of bags may be ruptured during the tipping and subsequent movement by dozer to the storage
location on the ore pad. The Mill's AO currently limits dust potential by requiring in Part ILB.Lc that
dusts from the ore loading areas may not exceed 15% opacity. Since the Uranium Material will be
relatively moist, with an average moisture content of approximately 22 to 77%, or 5.5 to 19 times higher
than the moisture content anticipated in the AO, it will have very little capacity to generate dust during
truck unloading or initial placement on the ore pad.
The SuperSaks are expected to be constructed of any of a number of types of polyolefins fibers.
Although previous experience indicates that prolonged storage of SuperSaks beyond several years may
Letter to Rusty Lundberg
August 30, 2013
Page 17 of 47
result in UV degradation of the fiber material, it is not anticipated that degradation of the SuperSaks will
be appreciable, due to the expected short ore pad storage anticipated for the Uranium Material. In any
case, the Mill's existing procedures are designed to manage airborne particulates from the ore pad
during any length of ore storage, and the stored Uranium Material will be sprayed with water sprays as
necessary to comply with the opacity requirements in the Mill's AO.
As demonstrated in Table 1, above, the Uranium Material contains levels of radionuclides comparable to
the levels of alternate feeds previously stored in bulk on the ore pad and processed at the Mill, with the
exception of somewhat elevated thorium isotopes. SFC has provided data indicating that, despite the
radionuclide concentrations measured in a finite number of samples of the Uranium Material, the actual
gamma field from the inventory of stored stacked SuperSaks at the Gore facility is very low. A
summary of available data is provided in Appendix B to this letter. The data indicated that the dose
rates at the surface of the SuperSaks were less than 1.6 mR/hr.
In any case, the Mill anticipates managing the SuperSaks under the existing Mill SOP for alternate feeds
with elevated thorium and/or gamma emitting radionuclides, tailored for the specific radiological
characteristics of the Uranium Material. The US NRC has previously approved this SOP for
management of high thorium alternate feeds, which the Mill has successfully implemented for the
management of other alternate feeds such as the Heritage Minerals alternate feed. A copy is provided in
Attachment 7 of the Revised August 2013 Amendment Request, which in included as Appendix to this
letter. The Mill plans to apply this SOP during handling and storage of the Uranium Material. As
discussed below, provisions of this SOP anticipate placement of a cover of soil of lower radionuclide
content alternate feed to provide shielding from potential gamma emanation from the Uranium Material.
This measure will be implemented regardless of the condition of the SuperSaks; that is, even if they
remain intact during their storage life on the Mill's ore pad.
Specific Comment 3b
Reference Sections 4.9 and 4.10 of the December 15, 2011Amendment Request.
Please clarify the intent of the statements in Section 4.9 of the Amendment Request on gamma radiation
and the discussion of radon and gamma impacts. Comment on the levels of gamma emissions expected
after Th-228 has established equilibrium with Th-232.
EFRI Response to Specific Comment 3b
The Th-228 data in the Application resulted from eight samples of material analyzed by Outreach
Laboratory in 2006 by Method LANL ER 200 M. The Outreach Analytical Laboratory data package,
dated March 13, 2006, contains the data for 8 dewatered raffinate sludge samples. Each of the 8
samples is a composite sample of the dewatered raffinate sludge. The composites were made by
collecting a grab sample of raffinate sludge from each bag of dewatered raffinate sludge during the
dewatering process. The grab samples from each cell (A through H) were composited to form a
representative sample of the dewatered raffinate sludge from that cell. All analyses are reported on a
dry-weight basis. The data were provided in Attachment 2 to the Application.
Letter to Rusty Lundberg
August 30, 2013
Page 18 of 47
As indicated in the laboratory data, the results for Th-228 produced by this method have relatively large
uncertainty ranges. That is, due to the error associated with the measurement method, it is uncertain
whether the actual Th-228 values are closer to equilibrium with Th-232 than indicated in the data.
Nevertheless, for purposes of the analysis below, we assume the level of equilibrium indicated by the
data.
The available data on the range of radionuclide activity levels in the Uranium Materials show a
substantial difference between the average Th-232 (approx 2,385 pCi/g) and the average Th-228 (approx
699 pCi/g). The half-life of the longest lived radionuclide in the Th-232 decay chain is 7.5 years (Ra-
228). Thus, the whole Th-232 series, and specifically Th-228, must come (close to) equilibrium with
Th-232 within a few decades.
There are several gamma emitters in the Th-232 decay chain below Th-228. Thus, the gamma radiation
dose from the Th-232 decay chain will increase when Th-228 grows toward equilibrium with its parent
Th-232. Assuming that the reported weighted average concentration of Th-232 in the Uranium Material
is 2,385 pCi/g, the gamma radiation dose from the Th-232 decay series when Th-228 grows into
equilibrium is estimated at approximately 37 [!Sv/hr (3.7 rnremlhr) on the surface of a large uncovered
area of the Uranium Material.
SFC has provided data indicating that the actual gamma field from stored stacked SuperSaks (that is, in
a reduced surface area) at the Gore facility is very low. A summary of available data is provided in
Appendix B to this letter. The data indicated that the dose rates at the surface of the SuperSaks were
less than 1.6 mR/hr. Based on the analysis above, these dose rates could be expected to increase to
approximately 3.7 mRIhr next to a large source, i.e. a large number of SuperSaks, over a few decades.
In any case, the gamma radiation, whether from the uranium or thorium decay chain, will behave in the
same way, and will be appropriately addressed by the Mill's radiation protection program. Gamma
radiation can be readily shielded by application of a lift or layer of lower activity material, such as clean
soil or other lower activity alternate feed.
Further, as discussed in the response to Specific Comment 3d, below, EFRI has previously developed a
specific SOP, approved by the US NRC, for receipt, unloading, stockpiling, processing and tailings
management for alternate feed materials with elevated levels of thorium. This procedure was originally
developed for the W.R. Grace alternate feed material, which had much higher concentration of Th-230
and Th-232 than the Uranium Material. A modified version of this SOP was also implemented for the
Heritage alternate feed material. EFRI has prepared a specific version of this SOP, with similar
protective measures as the NRC-approved SOP, suitable for the Uranium Material. The Uranium-
Material SOP and its protective measures are described in the response to Specific Comment 3d, and a
copy of the SOP is provided in Attachment 7 of the Revised August 2013 Amendment Request, which is
included as Appendix A to this letter. EFRI proposes to cover the stockpiled Uranium Material with a
covering of other lower activity alternate feed material of a minimum thickness to be determined by the
RSO based on scanning of the stockpiled SuperSaks after they are placed and stacked.
The Uranium Material has significant economic value to both EFRI and SFC; hence the schedule for its
processing will be prioritized. It is expected that the Uranium Material would be processed within a
Letter to Rusty Lundberg
August 30, 2013
Page 19 of 47
two-year period from receipt of the final shipments. As a result, the potential increase in gamma
radiation during this short time period is expected to be low, and can be appropriately managed under
Mill SOPs.
The text in Section 4.9 of the Application has been revised.
Specific Comment 3c
The radon discussion in Section 4.9 refers to radon-220, but the context indicates a reference to radon-
222 would have been more appropriate. The gamma discussion refers to Rn-226[sic}, when the· intent
appears to have been Rn-222. The discussion of gamma emissions from the thorium decay series
includes a reference to Th-238[ sic} and a statement that gamma emissions from the thorium series will
be low because of the disequilibrium between Th-232 and Th-228. While the statement about the
disequilibrium is correct when considering mill operations and worker exposures, it is not true for
longer term exposures from the tailings cell. Thorium-228 will essentially come into equilibrium with
Th-232 within a few decades. The intent of the statements on gamma radiation emissions needs to be
clarified. The potential gamma emissions from the tailings cell after Th-228 has come into equilibrium
with Th-232 needs to be discussed.
Please provide information on expected gamma radiation and radon emission rates from the Uranium
Material as delivered to the White Mesa site in its existing form (contained in Supersaks). Demonstrate
that such data support the conclusions presented in Section 4.10 that gamma radiation levels and radon
levels associated with the Uranium Material are within levels associated with other ores and alternate
feed materials processed in the past or which the Mill is or has been licensed to process.
EFRI Response to Specific Comment 3c
The Uranium Material may be approximately 20 years old or older. Therefore, the concentration of
Th-228 is should currently be near to equilibrium (i.e., calculated to be 90% of the Th-232
concentration) with Th-232. However, the radionuc1ide concentrations reported in the available data
show that Th-228 is not equilibrium with Th-232, as the weighted average Th-228 concentration is a
factor of 3.4 lower than Th-232).
Relative to Mill operations, the gamma radiation and radon emissions from the uranium series in
Uranium Material delivered to the Mill in its existing form from Sequoyah Fuels is lower than Colorado
Plateau ore. The weighted average concentration of Ra-226 in the Uranium Material is reported at 236
pCi/g. For comparison, the Ra-226 concentration from Colorado Plateau ores (0.25% U30 8) is
707 pCi/g and Arizona Strip ores (0.65% U30 8) is 1,838 pCi/g). Therefore, gamma radiation levels and
radon (radon-222) levels (both of which are derived from the decay of Ra-226) from the uranium series
in the Uranium Material is a factor of 3 lower than Colorado Plateau ores and a factor of 8 times lower
than Arizona Strip ores.
For gamma radiation from the thorium in the Uranium Material, the gamma radiation dose from Th-232
decay series is approximately 37 f,lSv/hr, or 3.7 mremlhr) (using the weighted average concentration of
Th-232 (2,385 pCi/g) and assuming that Th-232 and Th-228 (and subsequent decay products) are in
Letter to Rusty Lundberg
August 30,2013
Page 20 of 47
equilibrium. For comparison, the gamma radiation dose from Ra-226 (using the weighted average
concentration of Ra-226 (236 pCi/g) is approximately 3 [,tSvlhr (0.3 mremlhr). The gamma radiation
dose from the Th-232 decay series in equilibrium in the Uranium Material is therefore about a factor of
14 higher than that from the Ra-226 in the same material, but, even when combined with the gamma
dose from Ra-226 in the Uranium Material, is only a factor of 1.7 higher than that from Ra-226 in
Arizona Strip ores (23.4 [,tSvlhr or 2.34mremlhr). Therefore, although the potential gamma emissions
from the tailings cell after the Th-228 has come into equilibrium with the Th-232would be somewhat
higher than the potential gamma emissions from an equivalent volume of Arizona Strip ore, such
increased gamma emission would be insignificant given the total volume of Uranium Material (7,520
dry tons) compared to the total volume of Ce1l4A (1,856,000 dry tons).
SFC has provided data indicating that the actual gamma field from stored stacked SuperSaks at the Gore
facility is very low. A summary of available data is provided in Appendix B to this letter. The data
indicated that the dose rates at the surface of the SuperSaks were less than 1.6 mRlhr.
The text in Section 4.9 has been revised for clarity and to include the above corrections, as appropriate.
Specific Comment 3d
Section 4.10 of the Amendment Request indicates that gamma-radiation and radon levels associated
with the SFC Uranium Material are within levels of gamma radiation and radon levels associated with
other ores and alternate feed materials processed or licensed for processing at the Mill in the past, and
that gamma and radon exposures to workers will be managed in accordance with existing Mill standard
operating procedures. However, data for supporting those conclusions could not be located in
Denison IS Amendment Request or the associated attachments. Prior information on these parameters
obtained by SFC at the Gore, Oklahoma facility, including projected or actual radon concentrations in
the area around the dewatered raffinate sludge materials stored in Supersaks at the Sequoyah Gore
facility dewatered sludge storage area is available and may fulfill this need (e.g., see SFC 2004, SFC
2006, and NRC 2005.)
Reference Table 1 and the laboratory analysis reports in the "Radioactive Material Profile Record,
Dewatered Raffinate Sludge, February 2010" in Attachment 2 and Attachment 4.
According to the Radioactive Material Profile Record submitted by Denison, Th-232 levels in the
dewatered raffinate sludge (SFC Uranium Material) samples tested by Outreach Laboratory ranged
from 1,060 to 4,990 pCi/g Th-232 (weighted average oj2,385 pCi/g).
Information in Abdelouas 2006, based on data from Morrison 1991, NCRP 1993 and Cardarelli
undated, allows the following comparison between the average analytical results for uranium mill
tailings from different locations in Utah (for acid-leached uranium ores) and the SFC Uranium
Material:
Letter to Rusty Lundberg
August 30, 2013
Page 21 of 47
Analyte
Th-230
Th-232
Average Concentrations in
Uranium Mill Tailings or
Concentration Range in
Uranium Ores
Avg. Concentration: -873
pCi/g (32,300 Bq/kg) -
Monticello acid pile, uranium
mill tailings from
acid-leached ores)
Concentration Range: -0.2 to
2.2 pCi/g (8 to 80 Bq/kg) -
typical uranium ores
Analytical Results of Dewatered
Raffinate Sludge Analyte as
Furnished in Attachment 2
16,200 -74,400 pCi/g
1,060 to 4,990 pCi/g
(weighted average 0.12,385
pO/g)
ELI 2005 also reported the following analytical results for two samples obtained from the SFC Uranium
Material (dewatered sludge material) stored at the Gore, OK SFCfacility in July 2005:
Analyte Concentrations (Results reported on dry weight basis;
Received samples had -50% moisture content))
Th-230 30,900 pCi/g and 60,500 pOI/g)
Th-232 454 pC/g and 679 pCi/g
The above information suggests that concentrations of Th-230 and Th-232 in the SFC Uranium Material
appear to be elevated compared to their average level in Utah area uranium mill tailings for acid-
leached ores (likely typical of those that may have been processed at the White Mesa Mill), and relative
to the range of Th-232 levels found in typical uranium ores, respectively. The same situation may occur
relative to one or more other alternate feed materials previously accepted and processed at the Mill.
The potential for higher concentrations of Th-230 and Th-232 present in dust derived from the SFC
Uranium Material during processing and/or in dust from the resulting tailings to represent a pathway
for radiation exposures should be further evaluated. The implications of potential exposures from these
higher thorium concentrations (both Th-230 and Th-232) in the SFC Uranium Material with respect to
compliance with potentially applicable and relevant personnel health criteria should be further
assessed.
Compare the range of Th-230 and Th-232 levels (in pO/g) that could be expected to occur in the SFC
Uranium Material to the range of Th-230 concentrations and Th-232 concentrations in Colorado
Plateau uranium ores typical of those that are accepted and processed at the Mill and/or that are
present in typical uranium mill tailings in the Utah region (e.g., NCRP 1993; Abdelouas 2006;
Morrison 1991; Meisch 1963).
Letter to Rusty Lundberg
August 30, 2013
Page 22 of 47
Provide information on specific additional radiological protection requirements that may be
implemented at the White Mesa Mill when processing the SFC Uranium Material, including but not
limited to, additional protections/controls for limiting exposures to mill workers from increased radon
emission and associated radon daughter inhalation exposure levels [Note: The data in Table I,
information provided in Attachment 2 furnished by Denison, and other available data indicate that the
SFC Uranium Material could have considerably higher Th-230 and Th-232 levels than typical Colorado
Plateau uranium ore-derived uranium mill tailings in the Utah area and typical uranium ores,
respectively (e.g.-, Abdelouas 2006; Morrison 1991; Meisch 1963; NCRP 1993; Cardarelli undated.
EFRI Response to Specific Comment 3d
As discussed in Table 1, above, in the response to General Comment 1b, although the Th-230 and Th-
232 values in the Uranium Material are higher than those of Colorado Plateau ores, the Th-230 and Th-
232 values in the Uranium Material are below the maximum of the range of relevant radionuclide
activity concentrations of some already-approved alternate feed materials. As indicated in Table 1, since
the Th-230 and Th-232 levels in the Uranium Material are lower, the gamma radiation and radon
emissions from this Uranium Material will be correspondingly less than some alternate feed materials
that have been processed or licensed for processing at the Mill.
Further, as discussed in the response to Specific Comment 3c above, the Ra-226 concentration in the
Uranium Material is approximately 8 times lower than Arizona Strip ores. This means that the radon
emanations from the Uranium Material will be much less (8x less) than the radon emissions from the
same quantity of Arizona Strip ore. In addition, since gamma from conventional uranium ores comes
predominantly from Ra-226, the gamma from the Ra-226 in the Uranium Material will be approximately
8 times lower than the gamma from Ra-226 in a comparable amount of Arizona Strip ore. This
reduction in gamma from a lesser concentration of Ra-226 in the Uranium Material will offset most of
the gamma from increased concentrations of Th-232 and its daughters in the Uranium Material. The net
effect is that the gamma radiation dose from the Uranium Material will only be about 1.7 times higher
than the gamma radiation from an equivalent quantity of Arizona Strip ore. This level of gamma
radiation dose is well within the levels that are safely controlled by the Mill on a routine basis (some
loads of Arizona Strip ores can be two or three times higher than the average in uranium, and hence Ra-
226 concentrations, which would result in Arizona Strip ore emitting more gamma than the Uranium
Material).
The increased risks of exposure associated with elevated gamma and air particulates with higher Th-232
and Th-230 concentrations is addressed in the high thorium content SOP developed by EFRI and
approved by the US NRC, for receipt, unloading, stockpiling, processing and tailings management for
alternate feed materials with elevated levels of thorium. EFRI has tailored this SOP to the specific
radiologic characteristics of the Uranium Material. The Uranium-Material SOP and its protective
measures are described below, and a copy of the SOP is provided in Attachment 7 of the Revised
August 2013 Amendment Request, which is included as Appendix A to this letter. The SOP specific to
the Uranium Material includes the following additional protective measures:
Letter to Rusty Lundberg
August 30,2013
Page 23 of 47
Receipt, Unloading and Handling
• Requirement of a Radiation Work Permit ("RWP") with additional personnel protective
equipment and personnel monitoring during unloading and handling of the Uranium Material
• Additional airborne area sampling
• Additional radon monitoring
• Additional breathing zone sampling for routine work tasks and workers under an RWP during
ore unloading
• Cessation of all dumping activities when wind speeds exceed 20 mph
• Daily wet down of stockpiled Uranium Material on the ore pad until it is covered
• Covering of the uranium material with alternate feeds of lower thorium content of a thickness to
be determined by the RSO based on results from scanning of storage piles.
Processing
• Additional airborne area sampling
• Additional radon monitoring
• Additional breathing zone sampling for routine work tasks and workers under an RWP during
ore processing
Tailings Management
• Maintain the resulting tailings beneath pond liquid, tailings slurry or interim cover.
General
• Additional Personnel Protective Equipment ("PPE") and personnel hygiene required
Please see the SOP which is provided in Attachment 7 of the Revised August 2013 Amendment
Request, which is included as Appendix A to this letter, for detailed information on the procedures and
protective measures to be applied.
Specific Comment 3e
Information in Abdelouas 2006, based on data from Morrison 1991, allows the following comparison
between the average chemical composition of uranium mill tailings from different locations in Utah (jor
acid-leached uranium ores) and the SFC Uranium Material:
Analyte A verage Concentration in Analytical Results of Dewatered
Utah area uranium mill tailings Raffinate Sludge
as furnished in Attachment 2
As 74 ug/g 3,030 ug/g
Pb 158 ug/g 1,010 ug/g
Ba 1,010 ug/g 4,150 ug/g
Letter to Rusty Lundberg
August 30,2013
Page 24 of 47
Be Not Reported 18.7 ug/g
Information in Miesch 1963 (Tables 2 and 3) allows the following comparison between typical (mean)
chemical compositions of uranium ore from a uranium mine deposit and mill pulp samples from over
200 mine sites on the Colorado Plateau and the SFC Uranium Material:
Analyte Average Concentration in Analytical Results of Dewatered
Colorado Plateau Uranium Ores Raffinate Sludge as furnished in
and Mill Pulp Samples Attachment 2
As 120 ug/g 3,030 ug/g
Pb 31-90 ug/g 1,010 ug/g
Ba 550-750.ug/g 4,150 ug/g
Be -0.30-0.4 ug/g 18.7 ug/g
Additionally, ELI 2005 also reported the following analytical results for two samples obtained from the
SFC dewatered sludge material stored at the Gore, OK SFC facility in July 2005:
Analyte Concentrations (Results reported on dry weight basis;
Received samples had -50% moisture content))
As 1,370 ug/g and 1,470 ug/g
Pb 101 ug/g and 165 ug/g1
Ba 190 ug/g and 454 ug/l
Be 2.3 ug/g and 2.9 ug/g
1 Note: The reported values compare to a value of 1,0 I 0 ug/g Pb for a sample of the dewatered sludge reported in
Table I furnished by Denison.
2 Note: The reported values compare to a value of 4, 150 ug/g Ba for a sample of the dewatered sludge reported in
Table I furnished by Denison.
Letter to Rusty Lundberg
August 30, 2013
Page 25 of 47
Additionally, a sample of the raw raffinate sludge collected from Basin I of Clarifier A at the Gore,
OklahomafaGility in the RCRA Facility Investigation (RFl) contained 1,350 ug/g arsenic, 515 ug/g lead,
2,750 ug/g barium, and 4.12 ug/g beryllium.
The above information suggests that concentration of arsenic, beryllium, barium, and (possibly) lead in
the SFC Uranium Material appear to be elevated compared to Colorado Plateau-derived ores that may
have been processed at the Mill and/or present in uranium mill tailings in the Utah area. The same
situation may occur relative to one or more other alternate feed materials previously accepted and
processed at the Mill. The implications of elevated As, Be, and/or Pb levels in the Uranium Material
compared to ores and other alternate feed materials previously processed at the Mill and with respect to
potentially applicable and relevant personnel health criteria should be further assessed.
EFRI Response to Specific Comment 3e
As identified in the Amendment Request, Be, As, and Pb concentrations in alternate feed materials
already approved and processed at the Mill have had concentrations higher than those measured in the
Uranium Materials. Specifically, Be concentrations in previous alternate feed materials have ranged as
high as 33 mg/kg (ppm) or nearly twice the highest measured Be concentration in the Uranium Material
of approximately 18.7 mg/kg. Similarly, alternate feed materials previously processed at the Mill have
had As concentrations up to 7,800 mg/kg or more than twice the highest measured As concentration in
the Uranium Material of approximately 3,030 mg/kg, and other alternate feed materials have had Pb
concentrations up to 262,410 or 260 times higher than the highest measured Pb concentration of 1,010
mg/kg (ppm) in the Uranium Material.
Arsenic Toxicity
Inorganic As is toxic metal and a known human carcinogen by both the oral and inhalation exposure
routes. The differences in toxic potency among different inorganic chemical forms of As are usually
minor. At elevated exposure levels, inorganic As toxicity manifests as skin lesions, gastrointestinal
effects, encephalopathy, or peripheral vascular effects including cyanosis and gangrene. At lower
exposure levels, oral exposure is associated with hypertension, circulatory problems, and peripheral
neuropathy including numbness or pain (ATSDR, 2007)
Beryllium Toxicity
Be is a toxic metal and a known carcinogen. The principal exposure pathways for Be from Uranium
Material are inhalation, ingestion and dermal contact. Inhalation can cause irritation to the nose, throat,
lungs and mucous membranes. In some individuals, possibly due to genetic factors, Be may cause
chronic beryllium disease ("eBD"), a hypersensitivity or allergic conditions causing inflammation and
fibrosis resulting in a restriction of the exchange of oxygen between the lungs and the bloodstream
(Materion,2011). Be can also be taken into the body by ingestion of water and food or through the skin.
Although skin absorption does not appear to be a major pathway, skin contact can cause an allergic
dermal response in sensitive individuals and skin contact with Be dusts can result in sensitization
(NIOSH, 2008). The solubility of the Be compound affects the toxicity. The more soluble Be salts can
Letter to Rusty Lundberg
August 30, 2013
Page 26 of 47
cause irritant and allergic contact dermatitis. Delayed hypersensitivity dermal granulomas may be
caused by the less soluble forms of Be in contaminated wounds (Wambach, 2008).
Lead Toxicity
Pb is a toxic metal and classified by EPA as a probable human carcinogen. The principal exposure
pathways for Pb from the Uranium Material are inhalation, ingestion, and dermal (skin or eye) contact.
Inhalation can cause irritation to the nose, throat, lungs, and mucous membranes. Pb can also be taken
into the body by ingestion of water and food or through the skin. The solubility of the Pb compound
affects its toxicity. Symptoms of acute Pb poisoning via ingestion or inhalation include
weakness/exhaustion, insomnia, weight loss, abdominal pain, tremors, paralysis of wrist or ankles,
encephalopathy, gingival deposition, kidney disease and hypertension. Eye contact is associated with
short term eye irritation.
Occupational exposures to As, Be, or Pb might include dermal, inhalation and inadvertent ingestion.
Mill procedures for personnel protection from each pathway is discussed below.
The primary opportunities for personnel dermal or inhalation exposure occur material unloading and
storage. As discussed in the response to 1 b above, the Revised August 2013 Amendment Request has
been modified by incorporation of the Mill's SOP for potentially elevated thorium levels, tailored to the
specific radiological characteristics of the Uranium Material, to assure there are no additional effects to
worker safety or the environment. The requirements of the elevated thorium SOP, designed to control
and limit the dermal and inhalation exposure of personnel to thorium in the Uranium Material, will also
control and limit exposure to all metal constituents including As, Be and Pb. The Uranium-Material SOP
and its protective measures are described in the response to Specific Comment 3d, and a copy of the
SOP is provided in Attachment 7 of the Revised August 2013 Amendment Request, which is included as
Appendix A to this letter.
In addition to the radiation monitoring, covering of the material and other dust controls, radiation-related
Personal Protective Equipment ("PPE"), and special tailings management requirements in the SOP, as
discussed in responses to comments regarding thorium above, additional air monitoring and respiratory
protection requirements for As, Be, and Pb will be implemented.
The SOP includes specific provisions for continuous monitoring of area and breathing zone levels of
these metals by requiring that samples collected and analyzed on site for assessment of area and
breathing zone levels of radionuclides also be analyzed for these three metals. Per the SOP, this data
will be used to determine appropriate levels of respiratory protection for these metals, in addition to
radionuclides, for unloading, storage and material processing activities.
The full face respirator devices used when required for elevated levels of radionuclides or metals will
also provide protection from eye-related exposure to these metals.
With respect to inadvertent ingestion, normal uranium mill work rules and existing controls, designed to
prevent ingestion of radionuclides, would provide a reasonable assurance that these metals would not be
inadvertently ingested at levels likely to cause significant occupational risk.
Letter to Rusty Lundberg
August 30, 2013
Page 27 of 47
Therefore, based on EFRI's use of the Uranium Material specific SOP, there will be no potential for a
new or incremental increase in personnel exposure risk from these constituents.
References:
Centers for Disease Control. 2013. NIOSH Pocket Guide to Chemical Hazards
Centers for Disease Control. 2007. ATSDR Toxicological Profile for Arsenic
Centers for Disease Control. 2013. ATSDR Toxicological Profile for Lead
Hendricks, D.W. (2006). Water Treatment Unit Processes: Physical and Chemical. Boca Raton, Florida:
Taylor & Francis.
Materion. 2011. Beryllium Hydroxide Powder, Material Safety Data Sheet -No. D03. March 8, 2011.
MWH Americas (MWH). 2010. Revised Infiltration and Contaminant Transport Modeling Report,
White Mesa Mill Site, Blanding Utah. Prepared for Denison Mines. March.
New Hampshire Department of Environmental Services (NHDES). 2010. Beryllium: Health
Information Summary (ARD-EHP-35). Accessed 4122/13 at
des.nh.gov/organization/commissioner/pip/factsheets/ard/documents/ard-eph-35.pdf
U.S. Department of Health and Human Services, Public Health Service, National Toxicology Program
(NTP). (2011). Report of Carcinogens, Twelfth Edition.
Walsh, K. (2009). Beryllium Chemistry and Processing. ASM International.
Weast, R.c. (ed.). 1987. CRC Handbook of Chemistry and Physics, 68th edition.
Wiberg, N., Holleman, A.F. and E. Wiberg (Eds.). (2001). Inorganic Chemistry.
Specific Comment 3e.i
Compare the range of concentrations of the following constituents that could occur in the Uranium
Material with reported ranges of concentrations of the same constituents present in Colorado Plateau
uranium ores typical of those that are accepted and processed at the Mill and/or present in typical
uranium mill tailings in the Utah region (e.g., Abdelouas 2006; Morrison 1991; Meisch 1963):
• Arsenic;
• Barium;
• Beryllium; and
• Lead.
Letter to Rusty Lundberg
August 30,2013
Page 28 of 47
EFRI Response to Specific Comment 3e.i
As identified in Attachment 5, Table 4, Columns A and J of the December 2011 Amendment Request
(Comparison of Uranium Material to Tailings and Alternate Feeds), alternate feed materials previously
approved and/or processed at the Mill have had concentrations of As, Ba, Be, and Pb higher than those
measured in the Uranium Material. The headers of Column A and J in Table 4 have been corrected to
indicate units of mg/kg in place of mglL. Table 2, below, provides information on specific alternate
feed materials including, and in addition to, those reflected in Table 4 of Attachment 5. The source of
the materials has been clarified in Table 1 of Attachment 2 of the Revised August 2013 Amendment
Request.
As indicated in the table, the concentration of each of these four constituents in the Uranium Material is
well within the levels in previous alternate feed materials. In addition, as discussed in the response to
Specific Comment 3e, above the Mill will apply a Uranium-Material specific SOP designed to minimize
environmental dispersion of dusts, and provide personnel protection from inhalation and dermal
exposure to toxic metals in the Uranium Material. Based on EFRI's use of the Uranium Material
specific SOP, there will be no potential for a new or incremental increase in personnel exposure risk
from these constituents.
Table 2
Comparison of Analyte Concentrations in
rop.OS4 raDIum a erIa an revlOUS erna e ee s P ed U . M t . I d P . Alt t F d
Range of Uranium Range of Alternate Feed Source for Alternate Feed Information
Material Concentrations
Metal Concentrations· (mglkg dry)2
(mglkg)
Arsenic 3,030 3,300 to 7,800 (average 4,500) Cameco calcined product -customer
supplied data
1,640 to 3,280 Cameco fluoride product MSDS
10 to 3,000 (average 1,550) FMRI Application, March 2005
Barium 4,150 6,629 oxidized residues Molycorp Application, December 2000
6,884 unoxidized residues
Beryllium 18.7 8.5 to 33 (average 21) FMRI Application, March 2005
<10 to 2,040 (average 78) FMRI Application, March 2005
Lead 1,010 52,000 to 100,000 (drums) Molycorp Application, December 2000
1,544 to 262,410 (ponds) Molycorp Application, December 2000
1 Attachment 2 of the December 2011 Amendment Request (Radioactive Material Profile Record, and associated tables)
2 Selected concentrations for constituents found in characterization data for other alternate feed materials licensed for
processing at the Mill, for comparison purposes only.
Specific Comment 3e.ii
Discuss and compare the range of concentrations of the constituents listed in Specific Comment 2.c
above in the Uranium Material to potentially applicable/relevant RCRA hazardous wastelcharacteristic
waste limits, EPA recommended Soil Screening Levels (SSLs), including updated recommended Risk-
Based Concentration (RBC) levels (e.g., EPA 2012)for various types of soils issued by one or more EPA
Letter to Rusty Lundberg
August 30, 2013
Page 29 of 47
regional offices; relative to current, relevant "action levels" established for protecting workers from
exposure to elevated levels of constituents in air, such as beryllium, etc .... ; and/or other criteria as may
be appropriate.
EFRI Response to Specific Comment 3e.ii
The levels of constituents listed in Comment 2c are compared to the RCRA characteristic hazardous
waste concentrations in Attachment 4 of the December 2011 Amendment Request. As discussed in
Attachment 4, Section 1.0, of the Amendment request, and repeated here, per the Atomic Energy Act, as
amended, and 10 Code of Federal Regulations ("CFR") 40.4, ores with natural uranium content of 0.05
weight percent or higher are classified as source material and, as per 40 CFR Part 261.4, are exempt
from regulation under RCRA. EFRI performs the RCRA evaluation included in Attachment 4 for the
sake of completeness, and comparison to RCRA TCLP standards is not required.
SFC provided results from TCLP testing of 1 sample of the Uranium Material performed in December
2012. The TCLP results are provided in Attachment D.1cv of the Revised August 2013 Amendment
Request, which is included as Appendix A to this letter. Based on a comparison of the 2012 test results
to the RCRA toxicity characteristic thresholds as defined in Table 1 of 40 CFR Part 261.24(b), no
analyzed contaminant exceeded its respective TCLP threshold for the RCRA toxicity characteristic.
The levels of constituents listed in Comment 2c are compared to EPA soil screening levels in Table 4,
below.
Table 3 was extracted from the USEPA Pacific Southwest Region 9 Risk Screening Level ("RSL")
Tables as updated in November 2012. (No comparable regulatory levels were identified for Region 8.)
The Soil Screening Levels ("SSLs") presented are based on an assumption of a post-remediation
industrial use scenario, carcinogenic target risk levels of 1 in one million (lxlO-6) and a non-cancer
hazard index of 1. The assumption of industrial use is extremely-over conservative for the Mill site
which, in post-reclamation condition, will be transferred to the US Depaltment of Energy for oversight
in perpetuity.
No carcinogenic target risk levels have been proposed for Ba. As shown in the table, Ba is present in the
Uranium Material at levels more than 46 times lower than the lowest non-cancer SSL, which is, the SSL
based on a non-carcinogenic hazard index of 1.
Be is present in the Uranium Material at a level 368 times lower than the SSL associated with the
acceptable chronic/cancer risk, and approximately 106 times lower than the lowest SSL associated with
an acceptable non-carcinogenic risk.
As is present in the Uranium Material at levels above the proposed carcinogenic SSLs and three of the
four proposed non-cancer SSLs (ingestion, dermal, inhalation) in the table.
No carcinogenic target risk levels have been proposed for Pb. Pb is present in the Uranium Material at
levels above the proposed non-carcinogenic SSL based on a hazard index of 1.
Letter to Rusty Lundberg
August 30, 2013
Page 30 of 47
Constituent Uranium Ingestion
Material SL
(mglkg) TR=1.0E-6
(mgllq~-)
Arsenic,
inorganic 3.03E+03 3.2E+OO
No limit Barium 4.15E+03 proposed
Beryllium
and 1. 87E+0l No limit compounds proposed
Lead and l.OlE+03 No limit compounds proposed
Table 3
EPA Soil Screening Levels
Carcinogenic
Inhalation Carcinogenic
Dermal SL SL SL
TR=1.0E-6 TR=1.0E-6 TR=1.0E-6
~g) (mg/l{g) LIIlgIkg)
9.6E+OO 3.9E+03 2.4E+OO
No limit No limit No limit
proposed proposed proposed
No limit
proposed 6.9E+03 6.9E+03
No limit No limit No limit
proposed proposed proposed
Non-Cancer
Non-
Ingestion Dermal Inhalation carcinogenic
SL SL SL SL
HQ=1 HQ=1 HQ=1 HI=1
@gIk~ {!Ilg/k~ C~) (mWkg)
S.IE+02 1.SE+03 8.9E+04 3.8E+02
No limit
2.0E+OS proposed 3.0E+06 1.9E+OS
No limit
2.0E+03 proposed 1.2E+OS 2.0E+03
No limit No limit No limit
proposed proposed proposed 8.0E+02
As discussed in the responses to Specific Comment 3d, above, the Mill will require additional
procedures and worker protective measures that are included in a specific SOP for management of the
risks associated with increased thorium levels in the Uranium Material. As discussed in that response,
the measures include the following types of additional protections:
• Measures to minimize dusting and airborne transport
• Additional PPE
• Additional area and breathing zone monitoring
• Maintenance of resulting tailings under cover.
The protective measures identified in the attached SOP are designed to minimize exposures to workers
via inhalation, ingestion, and dermal exposure. The additional measures designed to minimize exposure
to radionuclides through these routes will also minimize exposure to toxic metals through these routes.
Because the Uranium Material, like other ores and alternate feeds will be processed in aqueous solutions
from the time it enters the leach circuit, the primary areas for potential worker exposure are the
unloading process, the ore pad, and the tailings area. Specifically, the attached SOP incorporates the
following protective measures for reduction of thorium exposure, which will also minimize exposure to
metals in the Uranium Material:
Ore Pad
• Additional airborne area sampling
• Additional breathing zone sampling for routine work tasks and workers under an RWP during
ore unloading
• Cessation of all dumping activities when wind speeds exceed 20 mph
• Daily wet down of stockpiled Uranium Material on the ore pad until it is covered
Letter to Rusty Lundberg
August 30, 2013
Page 31 of 47
• Covering of the uranium material with alternate feeds of lower thorium content of a thickness to
be determined by the RSO based on results from scanning of storage piles.
Processing
• Additional airborne area sampling
• Additional breathing zone sampling for routine work tasks and workers under an RWP during
ore processmg
Tailings Management
• Maintain the resulting tailings beneath pond liquid, tailings slurry or interim cover.
Specific Comment 3e.iii
Assess radiological and non-radiological impacts of releases from the facility to other media (including
release through air to adjacent uncontrolled lands) attributable to concentrations in Uranium Material
in excess of those previously authorized for receipt and processing at the White Mesa mill. Demonstrate
that the airborne effluent monitoring program is adequately designed and implemented to ensure that
acceptability of airborne releases to adjacent areas will be known and reported.
EFRI Response to Specific Comment 3e.iii
As stated in the December 2011 Amendment Request, and due to moisture contents as high as 77
percent, the Uranium Material has little potential for generating dust and particulates. The Mill's AO
currently limits dust potential by requiring in Part II.B.I.c that dusts from the ore loading areas may not
exceed 15% opacity. At the current time, Part II.B.4.h of the AO contemplates that the moisture content
of materials handled by front-end loading operations and truck-dumping operations are not less than 4%
by weight during these operations.
As stated in Section 4.2.1 and 4.2.7 of the application, the Uranium Material will be delivered in
SuperSaks in exclusive use trucks with poly-lined bottoms and sides, or flatbed style trailers with
sidewalls and tarp covers, which will be unloaded onto the ore pad for temporary storage pending
processing as is currently done for conventional ores and some alternate feed materials. The Uranium
Material will be unloaded and stored in a manner similar to conventional ore, with some added
protection required by the Mill's high thorium SOP, discussed below. In addition, the Uranium
Material will be relatively moist, with an average moisture content of approximately 22 to 77%, and has
been characterized (as noted in Attachment 2 of the December 2011 Amendment Request). As
mentioned in the response to General Comment 1 b, 6th bullet, above, this moisture content surpasses the
current moisture requirement for ores and feeds in the Mill's AO by a factor of 5.5 to 19 times.
As discussed in the responses to General Comment 1b and Specific Comments 3a through 3e above, the
chemical concentration of every constituent in the Uranium Material is well within the levels of other
alternate feeds previously licensed for and processed at the Mill. As discussed in the responses to
General Comment 1 b and Specific Comments 3a through 3e above, although all radionuclides in the
Uranium Material are within the levels of radionuclides in alternate feeds that have been licensed for
receipt and processing at the Mill, EFRI will apply a specific SOP for alternate feeds with elevated
Letter to Rusty Lundberg
August 30, 2013
Page 32 of 47
thorium levels, discussed in further detail in the response to Specific Comment 3d, above, to the
Uranium Material.
The existing environmental air monitoring system, required per License Condition 11.2 of the RML, and
summarized in Section 5.5 of the Mill's License Renewal Application (UMETCO 1991) has been
approved by the NRC and the State of Utah and meets the requirements identified in NRC regulatory
Guide 4.14 (NRC, 1980; Section 2).
The monitoring program referenced above includes high volume air sampling devices collecting
airborne radioparticulate data both upwind and downwind of the Mill. These environmental data are
composited regularly and analyzed quarterly, with results being reported semi-annually. These data are
assessed with respect to the 10 CFR 20, Appendix B, Table 2, Effluent Concentration Limits for
unrestricted areas, to ensure that site operational practices for controlling particulate radionuclides and
dust are protective of public health.
Similarly, the existing occupational health air monitoring program approved under License Condition
11.4 of the RML, and as described in the Technical TER for NRC License Amendment 7 (USNRC
August 1998), meets the requirements for monitoring particulate radionuclides at uranium mills (NRC,
1979) and has been approved by DRC. The TER for the NRC License Amendment 7 is included as
Appendix C to this letter.
EFRI has assessed many factors in developing the December 2011 Amendment Request, including the
adequacy of the existing stack emissions monitoring, fugitive emissions (dust) monitoring, and
environmental air particulate monitoring program. The Uranium Material chemical constituent
concentrations are within the range of those for other ores and alternate feed materials already processed
or licensed for processing, at the Mill (see response to General Comment Ib and Specific Comments 3a
through 3e above). Due to moisture contents as high as 77 percent, the Uranium Material has no
propensity to generate abundant dust sized particles.
Specific Comment 3e.iv
Discuss any additional requirements, activities, or measures that would be implemented at the White
Mesa Mill either during processing the Uranium Material, or following its processing, due to potentially
elevated concentrations of arsenic, barium, be1yllium, and/or possibly lead) compared to applicable
and relevant risk or health-based criteria (e.g., ACGIH 8-ltr average TLVs or other recommended
action levels, as applicable) and/or compared to concentrations typically present in uranium ores
processed at the Mill and/or present in Utah-area uranium mill tailings (Abdelouas 2006; Morrison
1991; Meisch 1963). For example, evaluate and discuss the potential need for additional controls to
limit individual exposures to elevated arsenic, beryllium, lead, etc .... levels that may be present in dust
that could be released from the SFC Uranium Material prior to, during, or following its processing; the
possible need for implementing more aggressive air sampling and/or material surface sampling criteria
for elements such as beryllium and lead.
Letter to Rusty Lundberg
August 30, 2013
Page 33 of 47
EFRI Response to Specific Comment 3e.iv
Please see response to Specific Comment 3d, above which addresses additional procedures and worker
protective measures that will be included in a specific SOP to be implemented at the Mill for
management of the risks associated with increased thorium levels in the Uranium Material. As
discussed in that response, the measures include the following types of additional protections:
• Measures to minimize dusting and airborne transport
• Additional PPE
• Additional area and breathing zone monitoring
• Maintenance of resulting tailings under cover.
The protective measures which will be implemented in the specific SOP for the Uranium Material, are
designed to minimize exposures to workers via inhalation, ingestion, and dermal exposure. The
additional measures designed to minimize exposure to radionuclides through these routes will also
provide protection from exposure to toxic metals through these routes.
Specific Comment 3/
Section 6.0 of Attachment 4 indicates that" ... One Uranium Material sample collected during 1994 and
one collected during 2003 were analyzed for RCRA TCLP constituents. No analyzed contaminant
exceeded its respective TCLP threshold for RCRA toxicity characteristic as defined in Table 1 of 40
CFR Part 261.24(b)." However the sample tested in 1994 using the TCLP procedures was apparently a
sample of raw raftinate sludge, not the dewatered raftinate sludge (Uranium Material) contemplated for
processing at White Mesa. Additionally, the sample of Uranium Material tested in 2003 is not described,
but appears to be sample ID MISC raft-filter press only leachate, SF03-278, which was extracted using
the ''7-day Distilled Water Leachate Test Procedures" in Texas Administrative Code (TAC) Chapter
335, Section 335.521 (d), rather than using the TCLP procedure. Because the extract derived from the
2003 dewatered sludge sample appears to have been obtained using distilled water, the extract results
cannot be directly compared to TCLP regulatory levels (see also discussion below). The implications of
using these different test methods and the use of raw vs. dewatered sludge sample, and the degree of
relevance of each set of test results with regard to comparison of the test results to TCLP regulatory
thresholds, and expected conditions at the White Mesafacility, need to be clearly stated.
Section 6.3.9 of NRC 2009 indicates the following: " ... To demonstrate compliance with 10 CFR Part
40, Appendix A, Criterion 6(7), SFC addressed nonradiological hazardous constituents of the byproduct
material in the Draft Corrective Actions Report (CMS), dated October 27, 1997. In the CMS report,
Section 2.5 and Tables 1 and 2 summarize source and soil sampling results. Treatability studies,
including conducting the toxicity characteristic leaching procedure (TCLP) extraction of sludges, were
performed, as well as metal analyses. Subsequent to the TCLP extraction, the results indicated that the
raftinate sludge [is] not characteristically hazardous."
According to Table 1 in Appendix 2, the analytical results reported under the column heading
"Dewatered Sludge Leachate" are the result of testing using the ''7-day Distilled Water Leachate Test
Procedures" included in Texas Administrative Code (TAC) Chapter 335, Section 335.521 (d). According
Letter to Rusty Lundberg
August 30, 2013
Page 34 of 47
to TAC Rule 335.507, the relevant "standard" against which test results from such testing should be
compared when assessing the (in)solubility of a constituent is the applicable groundwater MCLfor that
constituent, as listed in Table 3 of Appendix 1 ofTAC Rule 335.521 (d).
The TCLP Procedure (Method 1311) is much more widely recognized and accepted than the method
(See TAC 2012) that was used (7-day Distilled Water Leachate Test Procedures, TAC, Chapter 335,
Section 335.521 (d))for classifying the (in)solubility of the dewatered raffinate sludge material based on
the resulting leachate anaLytical resuLts. Rationale needs to be provided to support the test method that
was employed, rather than using the TCLP Procedure, since the latter procedure, for· example, uses an
acidic extractant that is more representative of the acidic conditions that exist in the tailings
environment. It therefore has not been demonstrated why the analytical data provided for the
"Dewatered Sludge Leachate" (6th column of Table 1 in Attachment 2) would be considered
representative of the conditions that the processed sludge material residuals would be exposed to if the
dewatered sludge were to be processed at the Mill.
Specific Comment 3f.i
Provide additional information regarding the selection of the test method used in extraction testing of
the SFC Uranium Material instead of using the Toxicity Characteristic Leaching Procedure (TCLP)
Method 1311. Discuss and qualify the comparisons between analytical results for the dewatered sludge
leachate presented in Table 1 compared to applicable regulatory thresholds (e.g., EPA or Utah
Drinking Water Standard MCLs vs. the TCLP Regulatory Levels that are listed in Table 1). Revise the
text in Section 6.0 of Attachment 4 to correctly state the specific test methods that were used for
analyzing each specific type of sludge sample tested (e.g., one TCLP test in 1994 on a raw sludge
sample; Texas Administrative Code 7-day distilled water leachate test in 2003 on a dewatered
sludge sample).
EFRI Response to Specific Comment 3f.i
As discussed in the Application, the Uranium Material is an ore that contains greater than 0.05% source
material, and is therefore exempt from RCRA, regardless of its process history or chemical composition,
and no further RCRA analysis is required. Also, the Uranium Material has been classified as lle.(2)
byproduct material by NRC under 40 CFR 261.4(a)(4). Because 11e.(2) byproduct material is also
exempt from RCRA, the Uranium Material is exempt from RCRA. The evaluations of characterization
data are provided for completeness despite the fact that the Uranium Material is categorically exempt
from RCRA for the two reasons stated above.
The 2003 leachate data that resulted from the Texas Administrative Code Chapter 335 Subchapter R
Appendix 4 "7-day Distilled Water Leachate Test Procedure" ("TAC Leachate Method") have been
deleted from Table 1. A TCLP Method 1311 leachate of the dewatered raffinate sludge was performed
in December 2012, and those data will be used in lieu of the TAC Leachate Method data previously
presented. Because the TAC Leachate Method data are no longer included, comparison to alternate
regulatory levels is no longer applicable.
The text in Section 6.0 of Attachment 4 will be revised.
Letter to Rusty Lundberg
August 30, 2013
Page 35 of 47
Specific Comment 3f.ii
Perform TCLP testing using EPA Method 1311 for representative sample of raffinate sludge material
proposed for processing at the White Mesa facility. Demonstrate that the raffinate sludge material is not
hazardous waste using results of this additional TCLP testing. Submit results of this additional TCLP
testing for the Division's considerations in demonstrating that the material is not hazardous waste and
in demonstrating compliance with 10 CFR40, Appendix A, Criterion 6(7) requirements relating to
non radiological hazardous constituents present in the sludge materials.
EFRI Response to Specific Comment 3f.ii
As stated in the response to specific comment 3f.i, the Uranium Material is categorically exempt from
RCRA, which includes determining if the Uranium Material is "hazardous waste" as requested in this
comment. For completeness, a TCLP Method 1311 leachate of dewatered raffinate sludge was
completed and analyzed for metals in December 2012. The data are presented in Table 1 of Attachment
2.
The nonradiological constituents present in the Uranium Material were determined using a TCLP
Method 1311 leachate which was analyzed for the eight EPA RCRA metals in December 2012. The
data are presented in Table 1 of Attachment 2. The TCLP leachate data show that there are no metals
which exceed the TCLP regulatory limits in Table 1 of Attachment 2. Of the eight metals analyzed,
only three were detected. The three metals detections are orders of magnitude below the TCLP
regulatory limit. Because the detections are significantly below the TCLP regulatory limit there is no
effect on the 10 CFR 40, Appendix A, Criterion 6(7) requirements relating to nonradiological
constituents present in the dewatered raffinate sludge. Additionally, the Uranium Material is physically
and chemically comparable to previously-approved alternate feed materials that the Mill has processed.
As discussed in more detail in Section 4.5 of the application, and the response to Specific Comment 3e,
above, all the constituents in the Uranium Material have either been reported to be, or can be assumed to
be, already present in the Mill's tailings system or were reported in other licensed alternate feeds, at
levels generally comparable to or higher than those reported in the Uranium Material.
Specific Comment 3f.iii
Provide additional information to justify the appropriateness of using the procedure in Texas
Administrative Code (TAC) Chapter 335, Section 335.521 (d) for testing the Uranium Material, instead
of using Method 1311, Toxicity Characteristic Leaching Procedure, referenced in 40 CFR Part 261,
Appendix II, for classifying the SFC Uranium Material for potential processing at the Mill. Demonstrate
that data from this testing of the SFC Uranium Material, which involved the use of distilled water as the
extractant, would be considered relevant and representative of the (acidic) liquid conditions that exist
within the tailings disposal cells at the Mill site.
Letter to Rusty Lundberg
August 30, 2013
Page 36 of 47
EFRI Response to Specific Comment 3f.iii
As previously stated in response to Specific Comment 3f.i, the 2003 leachate data that resulted from the
T AC Leachate Method have been deleted from Table 1. A TCLP Method 1311 leachate of the
dewatered raffinate sludge was performed in December 2012, and those data will be used for assessing
the Uranium Material in lieu of the TAC Leachate Method data previous presented.
Specific Comment 3fiv
Provide additional information on appropriate regulatory threshold levels that should be listed in Table
1 and used for evaluating/comparing the analytical results as reported for the Dewatered Sludge
Leachate and/or the "Dewatering Filtrate" in Table 1;
EFRI Response to Specific Comment 3f.iv
As previously stated in the response to Specific Comment 3f.i, the 2003 leachate data that resulted from
the T AC Leachate Method have been deleted from Table 1. A TCLP Method 1311 leachate of the
dewatered raffinate sludge was performed in December 2012, and those data will be used in lieu of the
T AC Leachate Method data previous presented. Because the TAC Leachate Method data are no longer
included, comparison to alternate regulatory levels is no longer applicable.
The Dewatering Filtrate data were provided for information purposes only. The data have been removed
from Table 1 in Attachment 2.
Specific Comment 3f v
Provide additional information on the specific analytical method and the nature of any matrix involved
in the analytical testing done with regard to the "Dewatering Filtrate" results provided in Table 1.
EFRI Response to Specific Comment 3f. v
The Dewatering Filtrate is the "water" produced when the raw raffinate sludge is pressed during the
dewatering process. The Dewatering Filtrate is the "pore water" that is in the raw, unfiltered, raffinate
sludge prior to the dewatering process in the filter press. As previously stated in the response to Specific
Comment 3f.iv, the Dewatering Filtrate data were provided for information purposes only. The data
have been removed from Table 1 in Attachment 2. For clarification, the analytical methods are EPA
methods or equivalent (Standard Methods, ASTM etc) used for water samples or TCLP leachate
samples.
Specific Comment 3g
The analytical report for the "Dewatering Filtrate" (5th column of Table 1 in Attachment 2) specifies
"Other" as the matrix involved in the testing. From the information provided it is unclear as to the
specific testing method and/or specific characteristics of any matrix that was involved in this particular
testing campaign. Additional information needs to be provided regarding these testing details to allow
the relevance of the resulting data to the proposed alternate feed processing request to be determined.
Letter to Rusty Lundberg
August 30, 2013
Page 37 of 47
Explain whether the holding time requirement specified in EPA SW-846 for mercury (28 days or less)
having been exceeded for the analytical tests for mercury completed on the "Dewatered Sludge",
"Dewatering Filtrate", and "Dewatered Sludge Leachate" (4 th through 6th columns of Table 1 in
Attachment2) invalidates these mercury test results. Alternatively, provide justification for the
acceptability of any of the reported mercury analytical results.
EFRI Response to Specific Comment 3g
With regard to the matrix and analytical methods for the Dewatering Filtrate, please see the response to
Specific Comment 3f.v.
The Dewatered Sludge Leachate and Dewatering Filtrate have been removed from Table 1, and the data
will not be used for characterization purposes. The mercury data for the Uranium Material (i.e. the
Dewatered Sludge) has been removed from Table 1 and will not be used for characterization purposes.
A total metals analysis was performed on the Uranium Material in December 2012 in conjunction with
the TCLP Leachate and metals analysis. The mercury data from the December 2012 total metals
analysis will be used for characterization. Because the data have been removed from use no further
justification is necessary.
Specific Comment 3h
Footnotes in Table 1 of Attachment 2 indicate that the dewatered sludge samples were obtained in May
2003. The analytical laboratory reports for mercury for this dewatered sludge testing included in
Attachment 2 also indicate that the samples were obtained on May 1, 2003, but were submitted for
laboratory analysis in October 2003 and were . analyzed for mercury content on 1111112003. This
information indicates that the EPA SW-846 (Chapter 3) -specified holding time requirement for
mercury analyses of 28 days or less was not met for the three mercury analytical results provided.
Reference Table 4 in "Review of Chemical Contaminant in SFC Uranium Materials to Determine the
Potential Presence of RCRA Characteristic or RCRA Listed Hazardous Waste, December 15, 2011 in
Attachment 5 and Sections 4.5.1 and 4.10 in the December 15, 2011 Amendment Request, and
Attachment 4:
Please correct or provide additional discussion of Table 4 in Attachment 5 and correct errors or
inconsistencies in information presented in that table. As a result of any changes made to Table 4,
please revise the conclusions in Section 4.5.1 (first paragraph, last sentence) of the amendment request
and Attachment 5, Section 10.0, item 4, if necessary.
EFRI Response to Specific Comment 3h
Regarding the exceeded mercury holding time, please see the response to Specific Comment 3f.
Attachment 5, Table 4 is correct, and the apparent discrepancy between Columns C "Estimated
Concentration range before processing" and Column D, "Estimated Average Concentration before
Letter to Rusty Lundberg
August 30, 2013
Page 38 of 47
Processing" is not an error. As described in the Notes to the table, specifically Note 2A, Column C
presents the measured concentrations of various constituents in the tailings, as analyzed during annual
tailings solution sampling.
However, by the time the tailings system would receive tailings from the Uranium Material, it would
likely also contain tailings from the large volume of FMRI alternate feed material which is on the ore
pad and currently being processed. At the time of the Application, no FMRI alternate feed material had
yet been processed, and the tailings compositions analyzed up to that time did not reflect the effects of
the tailings to be added from processing of the FMRI alternate feed. Note 2B explains that Column D
provides calculated concentrations of each constituent corrected to represent the conditions following
disposal of tailings from processing of the FMRI material. Since the FMRI alternate feed material
contains higher concentrations of some constituents and lower concentrations of others, than those
analyzed in previous tailings sampling events, the average concentration of some constituents in column
D could easily be outside the previously measured ranges.
No changes to the conclusions in Section 4.5.1 or Attachment 5 Section 10.0 are necessary.
Specific Comment 3i
Attachment 5, Table 4 appears to have many errors or inconsistencies. Column C gives the range of
constituent concentrations and Column D shows the average concentration. In some cases, the average
concentration in Column D is outside the range given in Column C. For example, the average cadmium
concentration in Column D is lower than the minimum value in Column C, while the average aluminum
concentration is above the maximum Column C value.
The percentages in Table 4, Column I appear incorrect. Footnote 8 explains that the Column I values
are meant to express the Column H values as percentages, but the calculation is incorrect. For example,
aluminum changes from 3,154 ppm to 3,806 ppm, but the percentage change is shown as 0.065% in
Column l. If changes are made to Table 4, the conclusions in Section 4.5.1 (first paragraph, last
sentence) of the amendment request and Attachment 5, Section 1 0.0, item 4 (which state that processing
the SFC Uranium Material will affect the concentrations in the tailings by no more than a fraction of
one percent) need to be reassessed and revised ifnecessary.
EFRI Response to Specific Comment 3i
In Attachment 5, Table 4, the apparent discrepancy between Columns C "Concentration Range in Mill
Tailings before Processing" and Column D, "Estimated Average Concentration in Mill Tailings before
Processing" is not an error. As described in the Notes to the table, specifically Note 2A, Column C
presents the measured concentrations of various constituents in the tailings, as analyzed during annual
tailings solution sampling. Column D presents estimated tailings concentrations adjusted to reflect
tailings from the current processing of alternate feed material from FMRI, as discussed below.
At the time the Application was submitted to DRC in 2011, none of the inventoried volume of alternate
feed material from FMRI had yet been processed, and the tailings compositions analyzed up to that time
did not reflect the effects of the tailings to be added from processing of the FMRI alternate feed. By the
Letter to Rusty Lundberg
August 30, 2013
Page 39 of 47
time the tailings system would receive tailings from the Uranium Material, it would also contain tailings
from the FMRI alternate feed material whose processing was initiated in 2013. Note 2B explains that
Column D provides calculated concentrations of each constituent corrected to represent the conditions
following disposal of tailings from processing of the FMRI alternate feed material. Since the FMRI
alternate feed material contains higher concentrations of some constituents, and lower concentrations of
others, than those analyzed in previous tailings sampling events, the average concentration of some
constituents in column D could easily be outside the previously measured ranges.
Column I and footnote 8 of Table 4 have been corrected, and revisions are indicated in red. The text of
the Application has been changed accordingly.
The units in the title of Column A have also been corrected to "mg/kg or ppm" to reflect that the data in
Column A resulted from totals analyses reported in mg/kg.
Specific Comment 3i.i
Reference Section 9.2 of Attachment 5 ("Review of Chemical Contaminants in SFC Uranium Material to
Determine Worker Safety and Environmental Issues and Chemical Compatibility at the Energy Fuels
Resources, Inc., White Mesa Mill"):
Provide additional information, including reference citations, to justify and support the identification of
an appropriate revised range of values of the distribution coefficient (Kd) for barium for representing
conditions at the White Mesa Mill Site, including the tailings environment in particular. Provide a
discussion of how this revised range of barium Kd's was used to assess the potential for barium to
impact groundwater beneathldowngradient of the tailings cells into which processed SFC' raffinate
sludge residuals would be placed.
EFRI Response to Specific Comment 3i.i
Please see response to Specific Comment 3j, below.
Specific Comment 3i.ii
Provide additional information and one or more reference citation( s) to support the statement included
in this section indicating that barium would be sufficiently represented by monitoring (groundwater )for
calcium.
EFRI Response to Specific Comment 3i.ii
Please see response to Specific Comment 3j, below.
iii. Provide additional information regarding the need to add barium as an additional monitoring
parameter in the facility's groundwater monitoring plan, especially given that, under acid conditions,
some (otherwise) water-insoluble barium compounds (e.g., barium sulfate) may become soluble and
move into groundwater (e.g., see US EPA, 1984), and given the Groundwater Quality Standard value of
2 mg/1 included in UA C R31 7-006.
Letter to Rusty Lundberg
August 30, 2013
Page 40 of 47
EFRI Response to Specific Comment 3i.iii
Please see response to Specific Comment 3j, below. Based on the information provided in that response,
EFRI does not believe that BA should be added as an additional parameter in the Mill's groundwater
discharge permit.
Specific Comment 3j
Section 9.2 of Attachment 5 ("Review of Chemical Contaminants in SFC Uranium Material to
Determine Worker Safety and Environmental Issues and Chemical Compatibility at the Energy Fuels
Resources, Inc., White Mesa Mill") includes a statement that the distribution coefficient (Kd) for barium
is 100 to 150,000 Ukg for sandy to clayey soil types and that Energy Fuels Resources, Inc., therefore
concludes that barium would be less mobile in groundwater than calcium. No reference sources are
cited to support either the Kd range stated or the conclusion made regarding the relative mobility of
barium compared to calcium, for conditions occurring at the White Mesa tailings Cells 4A and 4B.
Kennedy et al. (1992; Table 6.7), for example, lists a Kd value of 52 mUg for barium. EPA 2012
(Section 4.11 and Exhibit C-4 of Appendix C) provides a range of recommended Kd values for barium
as a function of pH (e.g., KJ = 52 mUg at pH= 8.0, Kd = 41 mUg at pH = 6.8, etc ... , with Kd values
decreasing with decreasing pH; the Kd value at pH = 4.9 is listed as 11 mUg.) Allison 2005 referenced
several citations reporting soil/water Kd values of barium all less than 10 Ukg, and cited several risk
assessment studies that used Kd values ranging from 11 to 52 Ukg. By comparison, the UDEQ
Statement of Basis for the Groundwater Discharge Permit indicates assumes Kd values for calcium
ranging from 5 to 100 Ukg (i.e., equal to or higher than those reported in the above references for
barium).
Additionally, Energy Fuels Resources, Inc., has not provided information to describe or substantiate
how the mobilization behavior for barium that may be expected to occur in the (e.g., acidic) tailings and
the near-field tailings embankment environment may differ from, or be similar to, that of calcium. EPA
( 1984), for example, reported that barium, when present in the form of barium sulfate in soils, is not
expected to be very mobile because of the formation of water-insoluble salts and its inability to form
soluble complexes with humic and fulvic materials, but noted, however, that, under acid conditions,
some of the water-insoluble barium compounds (e.g., barium sulfate) may become soluble and move into
groundwater.
Please provide information to describe or substantiate how the mobilization behavior for barium that
may be expected to occur in the (e.g., acidic) tailings and the nearjield tailings embankment
environment may differ from, or be similar to, that of calcium.
EFRI Response to Specific Comment 3j
Introduction of the Uranium Material into the Mill's tailings impoundments would marginally increase
the amount of Ba currently stored. Ba is present in the Uranium Material at concentrations of
approximately 4,150 mg/kg with Ba present primarily as barium sulfate.
Letter to Rusty Lundberg
August 30, 2013
Page 41 of 47
As discussed in the response to Specific Comment 3.e.i, above, barium chloride was used to remove
radium from treated raffinate solution at SFC. In waters where sulfate is present, radium is easily
removed by the addition of barium chloride: barium chloride dissolves and in the presence of sulfate, the
dissolved barium immediately re-precipitates as barium sulfate due to its very low solubility (0.022
mg/L in cold water; Weast, 1987). Dissolved radium co-precipitates with the barium sulfate (NEA &
IAEA, 2002). The radium co-precipitate sludge, containing barium sulfate, was periodically combined
with raffinate sludge in the impoundments that produced the Uranium Material. In the Uranium
Material, Ba is expected to be present as barium sulfate (BaS04). Once in the Mill circuit, barium sulfate
will remain as barium sulfate due to its very low solubility in concentrated sulfuric acid (0.025 mg/L;
Weast, 1987).
Barium sulfate is one of the most insoluble sulfate salts: the solubility of barium sulfate in cold water is
0.022 mg/L and in concentrated sulfuric acid only increases to 0.025 mg/L (Handbook of Chemistry and
Physics, 68th Edition). Geochemical modeling with the PHREdoxEQulibrium ("PHREEQC") modeling
tools using this solubility data and the geochemical conditions present in the Mill tailings (average
tailings sulfate concentration of 65 gIL) predicts that Ba from the Uranium Material will remain stable in
the tailings impoundment as the solid phase barium sulfate, and would not be expected to dissolve.
Given the low solubility of barium sulfate, especially in the presence of sulfate, there is, therefore, no
reasonable potential for Ba to migrate from the tailings into groundwater.
A search of available literature regarding Ba distribution coefficients (~), including the references
provided in DRC's comment, above, revealed that the Ba ~ can range from 0.3 to 164,000 L/kg for a
variety of geologic materials, with lower values (less than 2,800 L/kg) being more typical for soils and
sediments, and 10wer.KJ values measured with decreasing pH (Table 4).
EFRI's December 2011 Amendment Request indicated Ba .KJ values in the range of 100-150,000 L/kg
for sandy to clayey soils (Lintott and Tindall, 2007). Detailed review of this reference indicates that the
high .KJs reported in this reference are for pure clay . .KJs on the order of 1-390 L/kg were measured for
three sandy loams, and all tests were performed at a pH range of 7.7-8.3. Rai et al. (1984) provide a
range in Kd for sediments from 530-2,800 mL/g at pH 8. The references provided by UDEQ (Kennedy
et al., 1992, EPA, 2002 and Allison, 2005) all indicate Ba .KJs in the range 1-52 mUg, with .KJ
decreasing with decreasing pH. Thibault et al. (1990) reports .KJs in the range of 0.3-9.3 mUg, also
with ~ decreasing with decreasing pH.
Considering the low solubility of barium sulfate, there is no reasonable expectation that Ba would be
released from the tailings into groundwater. Further, the range in barium .KJ has considerable overlap
with the range in calcium .KJ (as reported in the DRC Statement of Basis for the GWDP: 5 -100 L/kg).
Given the comparable Kds for Ca and Ba, if a hypothetical change in geochemical conditions were to
occur causing the groundwater Ba concentration to increase, a concomitant increase in Ca concentration
would also be expected to occur. Therefore, Ba does not need to be added to the list of analytes that are
to be monitored at the site, and that groundwater Ca concentration can be used as an indicator of Ba
concentrations. If an increasing trend in Ca concentration is observed, analysis for Ba may, at that time,
be considered.
Letter to Rusty Lundberg
August 30,2013
Page 42 of 47
Further, the Mill monitors for a number of other dissolved constituents, such as chloride, fluoride, and
sulfate, each of which is an anion that is expected to have a higher mobility in groundwater than a cation
such as Ba. These anions can be used as indicators of potential tailings cell seepage, and because of their
mobility, as 'early warning' indicators for less mobile constituents such as Ba. Chloride in particular is a
conservative solute that is not retarded with respect to groundwater flow. As discussed in Davis and
DeWiest (1966) "All chloride salts are highly soluble, so chloride is rarely removed from water by
precipitation except under the influence of freezing or evaporation. Chloride is also relatively free from
effects of exchange, adsorption, and biological activity. Thus, if water once takes chloride into solution,
it is difficult to remove the chloride through natural processes."
Table 4. Literature Search of Barium KdS
Material pH Kd Reference
Clay 7.7-8.3 -1 -164,000 L/kg Lintott & Tindall, 2007
Sandy Loam 7.7-8.3 1-390 L/kg Lintott & Tindall, 2007
Sediment 8 530-2,800 mL/g Rai et al. (1984)
HFO Not specified 1.8-3.7 mL/g Allison et al. (2005); Table 7
Soil Not specified 11-52 mUg Allison et al. (2005); Appendix
A
Soil Not Specified 52 mL/g Kennedyet al. (1992)
Soil 4.9-8.0 11-52 L/kg EPA (2002); Exhibit C-4*
Sand 4.8 0.4-0.5 mL/g Thibault et al. (1990)
Smectite Clay 7.5-7.8 0.3-9.3 mUg Thibault et al. (1990)
* EPA (2002) provides pH-dependent K.! values; values shown in table are for the two extreme pHs provided.
REFERENCES:
Allison, J.D. and T.L. Allison. 2005. Partition Coefficients for Metals in Surface Water, Soil, and Waste.
u.S. Environmental Protection Agency, Office of Research and Development, Washington, DC
(EPN600/R-OS/074). July.
Davis, S.N. and R. J. M. DeWiest. 1966. Hydrogeology. John Wiley and Sons, 463 p.
Denison Mines (USA) Corp (Denison). 2011. Request to Amend Radioactive Materials License Denison
Mines (USA) Corp. White Mesa Uranium Mill San Juan County, Utah and Environmental
Report. Prepared for Utah Department of Environmental Quality. April.
Kennedy, W.E. and D.L. Strenge. 1992. Residual Radioactive Contamination from Decommissioning -
Technical Basis for Translating Contamination Levels to Annual Total Effective Dose
Equivalent. Final Report, NUREG/CR-SSI2, PNL-7794, Vol. 1. October.
Lintott, D. and M. Tindal. 2007. Estimation of a Generic Adsorption Coefficient Kd for Barium.
Prepared for BC Upstream Petroleum Environmental Task Group. July 3.
Letter to Rusty Lundberg
August 30, 2013
Page 43 of 47
Rai D, Zachara JM, Schwab AP, et al. 1984. Chemical attenuation rates, coefficients, and constants in
leachate migration. Vol. I: A critical review. Palo Alto, CA: Electric Power Research Institute, 6-
1 to 6-6. Report EA-3356.
Thibault, D.H., M.1. Sheppard and P.A. Smith. 1990. A Critical Compilation and Review of Default Soil
SolidlLiquid Partition Coefficients, ~, for use in Environmental Assessments. Atomic Energy of
Canada AECL-10125.
United States Environmental Protection Agency (USEPA). 2002. Supplemental Guidance for
Developing Soil Screening Levels for Superfund Sites. OSWER 9355.4-24. December.
Weast, R.c. (ed.). 1987. CRC Handbook of Chemistry and Physics, 68th edition.
If you have any questions, please contact me at [phone].
Yours very truly, ~/'-f'A..-'VV_I; ~~
NERGY FUELS RESOURCES (USA) INC.
Jo Ann Tischler
Manager, Compliance and Licensing
cc David C. Frydenlund
Dan Hillsten
John Hultquist
Ryan Johnson, Utah DRC
Harold R. Roberts
David E. Turk
Kathy Weinel
Attachments
Appendix A
Revised August 2013 Amendment Request
REQUEST TO AMEND
RADIOACTIVE MATERIAL LICENSE
DENISON MINESENERGY FUELS RESOURCES (USA)
CORPINC.
WHITE MESA URANIUM MILL
SAN JUAN COUNTY, UTAH
AND
ENVIRONMENTAL REPORT
for Processing of
Alternate Feed Material from
Sequoyah Fuels Corporation
Prepared for:
Utah Department of Environmental Quality
Division of Radiation Control
P.O. Box 144850
Salt Lake City, UT 84114-4850
Prepared by:
DeRis9R MiResEnergv Fuels Resources (USA) Gefplnc.
~~J:l....Streot. Suite 960225 Union Boulevard,Suite 600,
GeRveFLakewood, CO 80228e6
August 2013Deeember 2011
OeniSeA M AssEnergv Fuels AesourC€s (USA) Gefplnc.
TABLE OF CONTENTS
1.0 INTRODUCTION "" ... ",,"'''''''''''''''''''''''''''''''''''''''''''''''''''''''''.''''',., .......... , ............ "."" .. " .... " .... " ..... .,.1
1.1 WHITE MESA MILL. ............................................................................................................................................. 1
1..2 PROPOSED ACT10N ... -................ m , ............................. "" ....................................... _...... :. .. ........... __ ........... 1
1.3 PURPOSEOFAcTION........................................... .. ..... ----....... = .. -n==" ........ ___ ........................ 1
1.4 AMENDMENT ApPLICATION AND ENIIIBONMEMTAL RepORT ..... .-.-................................................................ 1
2.0 MATERIAL C0MPQSIT.ION AND VOLUME ....................................................... ""' ... " ..... "." ........ ,, •• 2
2.1 GENERAL. ............................................................................................................................................................ 2
2,2 HISTORICAL SUMMAJ1V Of SouBCES ........................................... __ .. .,., ................................................ -.......... 2
2.3 RADIOCHEMICAL DATA ......................................... nr ... "' ..... ",. ................. u ............... -......................... .,. ......... 3
2.4 PHVSICAL AND CHEMICAL DATA .............................. _ . .-........... .,., ... ,.,,,., .......................................................... 3
2.S COMPARISON TO OTHER ORES AND ALTERNATE FEED MJ\TERIALS liCENSED OR PROCESSING AT DiE
MILL 3
2.5.1 Ores and Alternate Feed Materiqls With Similar rlad/alao/cal CharacterIstics . __ ....... " . .,,,,,,, .... -"' ...... c.3
2.5.2 Ores and Alternate Feed Materiqls With Siml/arChelllTaal/Merol dlofpuerlsllc.s .. -.-.... .-.... ___ .......... ".,m4
3.0 REGULATORY CONSIDERATIONS ......... , ................. " ......... " .................. , ......... , .. , .......... ", ............ ,.4
3.1 ALTERNATE FEED GUIDANCE ........................................................................................................................... 4
3.2 URANIUM MA1ERIAL QUAI.JFIESA$ ·ORE" ....................................................................................................... 4
3.3 URANIUM MATERIAL NOT SUBJECT TO RCRA .•• ., .. ,................. .. ............................................... ., ........... ..4
3.3.1 General ........................................................................................................................................................... 4
3.3.2 6FRIIUDEQ lisled Hgzardolls Waste Prqrocof .. , ............ " ................... .,............ . ..................................... 5
3,3.3 ADolleonon of rile Usted HQ2oi'dous Woste Protocol .......... ".. .. ................................................................ (;
3.3A BadlaoC//ve Marer/a/ Profile RecoaL ................................................. , ...... :::.... .. .................................... 7
3.3.5 Conclusion ....................................................... _.............. " .. _._................... ......................... .. ... ~
3.4 URANIUM MATERIAL IS PROCESSED PRIMARILY FOR rrs SOIiRCe MATERIAL CONTENT "........ .." ...... ".8
4.0 ENVIRONMENT AFFECTED ..................................... " ..• ,!! ....... ,.' .... "' ...... " ..... 11 ...................... .,., ......... Ii
4.1 GENERAL ........................................................................................................ . " 8
4.2 TRANSPORTATION CONSIDERATIONS ...................................................... .-. .-.................................................... 10
4.2.1 BOckooloq and Made o{Trcmspol'wt/O(l ...... " ............................... ., ......... = ........ _.. .. ........ _ ...... 10
4.2.2 TroflSnortarlOlllmQQers ............................................................................................................................... 11
4.2.3 TrallSportarlon Accldellfs ................... ,.. _._._. _ ............. ., .................................................................. ., ...... .12
4.3 STORAGE ..................................................................... 1 ........................................................................ -....... .-.... 13
4.3..1 Mannero[Slorage........................... .. .... _,.._ ......... _ .... _ ... _.: ..................................................................... J3
4.3.2 (nvlrcnmentallmpa/;!$ Associated With Storoge ................................ ., ............................ ., ......... .-...... , .. 13
4.4 PROCESS .................................................................. . ....... _ ........................... ,.,."' ...... _ ............... -.............. 13
4.4.1 Mill Accidents and £mgrgellCV Response ........................................... : ....... ,,, ... ,. .................. : ................... 14
iI.S COMPATIBIUTY WI11-I MILL TAILINGS ........................................ " ................. _ ............ _._._................. .. ......... 14
4..5..1 PhysIcol Cprnootlbl/lty.............................. .. .............................................................................................. 14
4,5.2 CaDOe/tv and Tl1rouq!Jmlt............................................................................... . ........... _........... ..,= ... ,15
4.5.3 MI/I Ta/llnm Closure and Reciomo(/a/J ................. _ ...... ".n m .. "" .................... .,_ ............... ., .... 15
4.6 GROUNDWATER ........................................................................................................... _ .. _ .............................. ,.1G
4.7 SURFACE WATER ............................................................. _" ..................... =, ........ ., ...... -.......... .,. ..... c-_ ......... .,.16
4.8 AIRBORNE RADIOLOGICAL IMPACTS ............................... , ...................................... _ ...................................... 17
4.9 RADON AND GAMMA IMPACTS ............................ ........ .._ ................................... ,. .. , ....... -._ ..... _ .. _ ... .,_ ... 17
4.10 SAFETY MEASURES ................................................... .. ........... .,.,_ .......................................................... 1M-+
4.10.1 General ................................................................................................................................................. 18P
4.1Q.2 Radiation Safety, ......... " .. .,........................ .. ......... ., ............................................................................. 18
Request to Amend Radioactive Malerials License
geAl~IReoSEnerqv FuelS Resources (USA) ~Inc.
4.10.3 OCCU{lflliona/ SafelV ................................... j .............. ll ................................................ · ........................ 1$$8
4.10.4 Vehicle Scan ......................................................................................................................................... 20lB
4.11 LONG TERM IMPACTS ....................................... "' ••• ", ......................... oo ............................ _ ••• _ ............... , ...... 2~
4.12 OTHER OPERATIONAL CONSIDERATIONS .................. ------1--... ' ................................... " ......................... 20±9.
4.13 ADDEO ADVANTAGE OF RECYCLING .......................................................................................................... 2019
4.14 CONSIDERATION OF ALTERNATIVES ....................... ~ ......... "0' ...... : .. "' .... " ...... ".,,--.-.-. .. .......... _ .. ___ ... 2~
5.0 CERTIEICATIQN " ....... " ........... "" ... " .. " .................. ,.." .... "." ........... " .. , .......... , ................... " ........... 22AA
ATTACHMENTS
Attachment 1 Sequoyah Fuels Corporation (SFC) Gore Facility Location
Attachment 2 Radioactive Material Profile Record and Affidavit
Attachment 3 DenisonEFRl/UDEQ Protocol for Determining Whether Alternate Feed Materials
are RCRA Listed Hazardous Wastes
Attachment 4 Review of Chemical Contaminants in SFC Uranium Material to Determine the
Potential Presence of RCRA Characteristic or RCRA Listed Hazardous Waste
Attachment 5 Review of Chemical Contaminants in SFC Uranium Material to Determine Worker
Safety and Environmental Issues and Chemical Compatibility at the Denison
EFRI Mines White Mesa Mill
Atla'C~meAt i> Cros!! I "dex: tQ DRC I htarrQgatory Ternplate lor Review of License Amendment
Requests and Environmental Reports l,mder UAC R313·24
AttacHment 7 Energy FuelS Resources (USA) Inc. Standard Operating Procedure SFC
Allernate Feed Management
Request to Amend Radioactive Materials License Ii
~Energy Fuels Resources (USA) Geijllnc.
1.0 INTRODUCTION
1.1 White Mesa Mill
GaR seA-MiAesEnergy Fuels Resources (USA) Gefj3lnc. ("DoAisoAEFRI") operates the White
Mesa Uranium Mill (the "Mill") located approximately six miles south of Blanding, Utah. The Mill
processes natural (native, raw) uranium ores and alternate feed materials. Alternate feed
materials are uranium-bearing materials other than natural ores, that meet the criteria specified
in the United States Nuclear Regulatory Commission's ("NRC's") Interim Position and Guidance
on the Use of Uranium Mill Feed Material Other Than Natural Ores (November 30, 2000) (the
"Alternate Feed Guidance"). Alternate feed materials are processed as "ore" at the Mill primarily
for their source material content. As a result, all waste associated with this processing is 11 e.(2)
byproduct material.
1.2 Proposed Action
This is a request for an amendment to State of Utah Radioactive Materials License No. UT
1900479 to authorize receipt and processing of certain uranium containing materials. These
materials are raffinate sludges resulting from purification and conversion of natural uranium
concentrates (yellowcake) in a former uranium conversion facility owned by the Sequoyah Fuels
Corporation ("SFC") near Gore, Oklahoma (the "Facility" or the "Site"). For ease of reference,
the uranium bearing material that results from this process, described further in Section 2, is
referred to herein as "Uranium Material".
1.3 Purpose of Action
The Uranium Material contains greater than 0.05% uranium on both a wet and dry basis. The
NRC issued Source Material License SUB-1010 to SFC for the Uranium Material in 1970. After
1993, the license was modified to a reclamation license and the regulatory authority for the SFC
facility and the Uranium Material was transferred to the State of Oklahoma Department of
Environmental Quality.
From 1970 to 1993, the facility chemically converted uranium ore concentrates (yellowcake) to
uranium hexafluoride under NRC Source Material License Number SUB-1010. From 1987 to
1993, other circuits at the facility also converted depleted uranium hexafluoride into depleted
uranium tetrafluoride. The Uranium Material consists only of residuals from the conversion of
natural uranium yellowcake to uranium hexafluoride.
DOAisOA EFRI has been requested by SFC to make this application to process the Uranium
Material as an alternate feed material at the Mill and to dispose of the resulting tailings in the
Mill's tailings impoundments as 11 e.(2) byproduct material. Approval of this application will allow
the recovery of valuable uranium, a resource that would otherwise be lost to direct disposal and
will afford SFC a cost-effective and productive mechanism for managing the material generated
as part of the Facility reclamation.
1.4 Amendment Application and Environmental Report
This application is intended to fulfill the requirements of an application for an amendment to the
Mill's Radioactive Materials License set out in Utah Administrative Code ("UAC") R313-22-38
and includes the Environmental Report required by UAC R313-24-3 to be contained in such an
application.
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For ease of review, this application contains a cross reference to the Utah Division of Radiation
Control's ("DRC's") Interrogatory Template for Review of License Amendment Request and
Environmental Report under UAC R313-24 that was provided to DeRisoREFRI. The cross
reference is provided in a table format in Attachment 6.
2.0 MATERIAL COMPOSITION AND VOLUME
2.1 General
The Facili!y is a former uranium conversion facility that operated from 1970 to 1993. The facility
was constructed and operated by SFC, as a subsidiary of Kerr-McGee Nuclear Corporation. In
1983 Kerr-McGee Nuclear Corporation split into Quivira Mining Corporation and SFC, which
maintained control of the Facility. SFC was sold to General Atomics Corporation in 1988 which
continued to operate the Facility until 1993.
From 1970 to 1993, the Facility chemically converted uranium ore concentrates (ye"owcake) to
uranium hexafluoride under NRC Source Materials License Number SUB-1 010. From 1987 to
1993, the Facility also converted depleted uranium hexafluoride into depleted uranium
tetrafluoride in a different circuit. The Uranium Material consists only of residuals from the
conversion of natural uranium yellowcake to uranium hexafluoride.
2.2 Historical Summary of Sources
The Uranium Material consists of the raffinate sludge, produced as a byproduct of the
yellowcake conversion process described below.
This yellowcake conversion process included two primary purification steps: digestion followed
by solvent extraction. Digestion occurred by dissolving the uranium in nitric acid. The resulting
slurry was subjected to solvent extraction using tributyl phosphate diluted with n-hexane.
Process conditions were controlled to extract uranium into the organic phase. The milling
impurities remained in the aqueous phase, a dilute nitric acid mixture termed raffinate.
The aqueous raffinate stream is primarily a solution of nitric acid, metallic salts, and trace
quantities of uranium and radioactive decay products of natural uranium, primarily Th-230 and
Ra-226. The raffinate stream also contained trace quantities of Th-232 which is often found in
natural uranium ores. The aqueous raffinate stream was combined with spent sodium
hydroxide from nitrous oxide scrubber systems and waste sodium carbonate solutions. The
untreated raffinate stream from solvent extraction was pumped to an impoundment and allowed
to cool. Anhydrous ammonia was added to the raffinate solution to convert the dilute nitric acid
to ammonium nitrate. The addition of the anhydrous ammonia also increased the pH of the
raffinate solution causing the metallic salts and trace quantities of uranium, thorium, and radium
to precipitate and settle out in the impoundments as raffinate sludge.
DORisOR EFRI has been requested by SFC to make this application to process the Uranium
Material as an alternate feed material at the Mi" and to dispose of the resulting tailings in the
Mi"'s tailings impoundments as 11 e.(2) byproduct material, in an effort to provide SFC with an
option for ultimate processing and disposal of the Uranium Material. By providing SFC with the
option of processing the Uranium Material at the Mi", SFC wi" be given the option of recycling
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DSRiooA MillosEner9V Fue!s RaSOlltCflS (USA) Gerplnc.
the Uranium Material for the recovery of valuable uranium, a resource that would otherwise be
lost to direct disposal.
SFC has requested that Denisen EFRI recycle the uranium material and has asked that
Denison EFRI submit this Amendment Request. SFC estimates that the total volume of
Uranium Material is expected to be approximately 11,112 tons gross weight at 45.1 percent
R'lOistl:JFe solids (5,011 tons dry weight). It has been Denison's EFRI's experience with other
alternate feeds from comparable sources that the initial estimate may increase by as much as
50 percent or more by the time of receipt (due to factors such as under-estimation of numbers of
containers, changes in moisture content, and other variables). Therefore, this request for
Amendment is for approval of up to 16,700 tons gross weight (7,520 tons dry weight) of
Uranium Material, to ensure that all the Uranium Material is covered by this Amendment.
2.3 Radiochemical Data
As noted, the process history demonstrates that the Uranium Material results from the
precipitation of impurities during the refining and conversion of natural uranium concentrates to
uranium hexafluoride. SFC has estimated that the current Uranium Material has a uranium
content ranging from 0.7 to 1.0 dry weight percent natural uranium or 0.8 to 1.2 dry weight
percent U30 B; and 0.3 to 0.5 wet weight percent natural uranium or 0.4 to 0.6 wet weight
percent U30 B• Thorium-232 content will likely range from 1.0 to 4.5 dry weight percent and may
be expected to average approximately 2.2 dry weight percent. A more detailed radiological
characterization of the Uranium Materials (see Section 2.5.1, below) is contained in the
Radioactive Materials Profile Record ("RMPR") (Attachment 2). The radionuclide activity
concentration of the Uranium Material is comparable to Arizona Strip breccia pipe ores and
alternate feed materials which the Mill is currently licensed to receive (see Section 2.5.1, below).
2.4 Physical and Chemical Data
Physically, the Uranium Material is raffinate sludge with no free liquid, consisting of moist solids
containing residual amounts of uranium and other metals. The chemical characterization data
for the Uranium Materials is set out in the RMPR (Attachment 2). As with the radionuclides and
as discussed in more detail in Section 4.4 below, all the chemical constituents in the Uranium
Material have either been reported to be, or can be assumed to be, already present in the Mill's
tailings system or were reported in other licensed alternate feeds, at levels generally
comparable to or higher than those reported in the Uranium Materials.
2.5 Comparison to Other Ores and Alternate Feed Materials Licensed for Processing
at the Mill
2.5.1 Ores and Alternate Feed Materials With Similar Radiological Characteristics
With an average uranium content of approximately 0.95 to 1.23 percent U30 B, the Uranium
Material is comparable to a high-grade Arizona Strip breccia pipe uranium ore. Arizona Strip
ores typically average from about 0.40 percent to over 1 percent U30 B.
The estimated average content of total natural thorium ("Th-nat") of approximately 2.2 dry
weight percent is higher than normally encountered with natural ores but well within the range of
previously licensed alternate feed materials at the Mill.
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For example, the average concentrations of Th-nat in the W.R. Grace and Heritage Minerals
alternate feed materials averaged approximately 7.27 percent and many other alternate feed
materials have had elevated concentrations of Th-nat. The Uranium Material will be handled at
the Mill under the Mill's radiation safety program in a manner appropriate for such materials.
2.5.2 Ores and Alternate Feed Materials With Similar Chemical/Metal Characteristics
The Uranium Material is physically and chemically comparable to previously-approved alternate
feed materials that the Mill has processed. As discussed in more detail in Section 4.5 below, all
the constituents in the Uranium Material have either been reported to be, or can be assumed to
be, already present in the Mill's tailings system or were reported in other licensed alternate
feeds, at levels generally comparable to or higher than those reported in the Uranium Material.
3.0 REGULATORY CONSIDERATIONS
3.1 Alternate Feed Guidance
The Alternate Feed Guidance provides that if it can be determined, using the criteria specified in
the Alternate Feed Guidance, that a proposed feed material meets the definition of "ore", that it
will not introduce a hazardous waste not otherwise exempted (unless specifically approved by
the EPA (or State) and the long-term custodian), and that the primary purpose of its processing
is for its source material content, the request can be approved.
3.2 Uranium Material Qualifies as "Ore"
According to the Alternate Feed Guidance, for the tailings and wastes from the proposed
processing to qualify as 11 e.(2) byproduct material, the feed material must qualify as "ore". NRC
has established the following definition of ore: Ore is a natural or native matter that may be
mined and treated for the extraction of any of its constituents or any other matter from which
source material is extracted in a licensed uranium or thorium mill. The Uranium Material is an
"other matter" which will be processed primarily for its source material content in a licensed
uranium mill, and therefore qualifies as "ore" under this definition. Further, the uranium
concentration of the Uranium Material is greater than 0.05 percent on both a wet and dry basis,
and the Uranium Material is an ore, the entire mass of Uranium Material is thergfore Source
Material.
3.3 Uranium Material Not Subject to RCRA
3.3.1 General
The Alternate Feed Guidance currently provides that if a proposed feed material contains
hazardous waste, listed under Section 261.30-33, Subpart D, of 40 CFR (or comparable RCRA
authorized State regulations), it would be subject to EPA (or State) regulation under RCRA.
However, the Guidance provides that if the licensee can show that the proposed feed material
does not consist of a listed hazardous waste, this issue is resolved. NRC guidance further
states that feed material exhibiting only a characteristic of hazardous waste (ignitability,
corrosivity, reactivity, toxicity) that is being recycled, would not be regulated as hazardous waste
and could therefore be approved for extraction of source material. The Alternate Feed
Guidance concludes that if the feed material contains a listed hazardous waste, the licensee
can process it only if it obtains EPA (or State) approval and provides the necessary
documentation to that effect. The Alternate Feed Guidance also states that NRC staff may
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Denison MinesEnergy Fuels Resources (USA) ~Inc.
consult with EPA (or the State) before making a determination on whether the feed material
contains listed hazardous waste.
Subsequent to the date of publication of the Alternate Feed Guidance, NRC recognized that,
because alternate feed materials that meet the requirements specified in the Alternate Feed
Guidance must be ores, any alternate feed materials that contain greater than 0.05% source
material are considered source material under the definition of source material in 10CFR 4004
and hence exempt from the requirements of RCRA under 40CFR 26104(a)(4). See Technical
Evaluation Report, Request to Receive and Process Molycorp Site Material issued by the NRC
on December 3, 2001 (the "Molycorp TER"). As a result, any such alternate feed ores are
exempt from RCRA, regardless of whether they would otherwise have been considered to
contain listed or characteristic hazardous wastes. Since the Uranium Material contains greater
than 0.05% source material, it is exempt from RCRA, regardless of its process history or
constituents, and no further RCRA analysis is required. Further, the Uranium Material has been
classified as 11 e.(2) byproduct material by NRC under 40 CFR 26104(a)(4) under SFC's License
Amendment 29, dated December 11, 2002. 11 e.(2) byproduct material is exempt from RCRA,
and for this reason also the Uranium Material is exempt from RCRA.
Nevertheless, because the Alternate Feed Guidance has not yet been revised to reflect this
position recognized by NRC in the Molycorp TER, and because it is not necessary to rely on the
NRC's classification of the Uranium Material as 11 e.(2) byproduct material (which in fact should
be considered determinative of this issue) Denison EFRI will demonstrate below that, even if the
Uranium Material were not considered source material or 11 e.(2) byproduct material, and as
such exempt from RCRA, the Uranium Material would not, in any event, contain any RCRA
listed hazardous wastes, as required under the Alternate Feed Guidance as currently worded.
3.3.2 Denis9nEFRI/UDEQ Listed Hazardous Waste Protocol
In a February, 1999 decision regarding the Mill, the Atomic Safety and Licensing Board
Presiding Officer suggested there was a general need for more specific protocols for
determining if alternate feed materials contain hazardous components. In a Memorandum and
Order of February 14, 2000, the full Commission of the NRC also concluded that this issue
warranted further staff refinement and standardization. Cognizant at that time of the need for
specific protocols to be used in making determinations as to whether or not any alternate feeds
considered for processing at the Mill contained listed hazardous wastes, EFRIDenison took a
proactive role in the development of such a protocol. Accordingly, Denison EFRI established a
"Protocol for Determining Whether Alternate Feed Materials are Listed Hazardous Wastes"
(November 22, 1999). This Protocol was developed in conjunction with, and accepted by, the
State of Utah Department of Environmental Quality ("UDEQ") (Letter of December 7, 1999).
Copies of the Protocol and UDEQ letter are provided in Attachment 3. The provisions of the
protocol can be summarized as follows:
a) In all cases, the protocol requires that Donison EFRI perform a source investigation to
collect information regarding the composition and history of the material, and any
existing generator or agency determinations regarding its regulatory status;
b) The protocol states that if the material is known --by means of chemical data or site
history --to contain no listed hazardous waste, Denison EFRI and UDEQ will agree that
the material is not a listed hazardous waste;
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~~Energy Fuels Resources (USA) Geij1lnc.
c) If such a direct confirmation is not available, the protocol describes the additional
chemical process and material handling history information that Denison EFRI will collect
and evaluate to assess whether the chemical contaminants in the material resulted from
listed or non-listed sources;
d) The protocol also specifies the situations in which ongoing confirmation/acceptance
sampling will be used, in addition to the chemical process and handling history, to make
a listed waste evaluation;
e) If the results from any of the decision steps indicate that the material or a constituent of
the material did result from a RCRA listed hazardous waste or RCRA listed process, the
material will be rejected; and
f) The protocol identifies the types of documentation that Donison EFRI will obtain and
maintain on file, to support the assessment for each different decision scenario.
The above components and conditions of the Protocol are summarized in a decision tree
diagram, or logic flow diagram, included in Attachment 3, and hereinafter referred to as the
"Protocol Diagram".
3.3.3 Application of the Listed Hazardous Waste Protocol
Donison EFRI has conducted a RCRA evaluation of the Uranium Material and, specifically,
applied the Listed Hazardous Waste Protocol to the Uranium Material. A copy of the analysis is
included as Attachment 4. The analysis evaluated the following regulatory history to develop
the conclusions enumerated below.
The NRC issued Source Material License SUB-1010 to Sequoyah Fuels in 1970 for conversion
processing of natural uranium concentrates/yellowcake, which process resulted in the
generation of the Uranium Material. This License was modified by the NRC from an operational
to a reclamation license on September 30, 1990.
In 1993, the U.S. Environmental Protection Agency ("EPA") issued an Administrative Order on
Consent ("AOC") requiring that the Facility should be remediated pursuant to RCRA. Pursuant
to the AOC, SFC prepared a RCRA Facility Investigation Report and RCRA Corrective Action
Plan.
On December 11, 2002, NRC issued Amendment 29 to SFC's Source Material License,
classifying the Uranium Material as 11 e.(2) byproduct material. In a communication to EPA in
2006, NRC affirmed that:
1. the Site was subject to the regulatory oversight of NRC,
2. the Site therefore was to be decommissioned under 1 OCFR Part 40, Appendix A, and
3. NRC would ensure that the contaminants addressed by the AOC would be properly
managed.
NRC's 2002 communication requested that EPA close their AOC. EPA subsequently
terminated the AOC in December 2009.
The Uranium Material, which has materially not changed in form or content since first being
produced in 1970, remains definitional source material as per 40 CFR Part 261.4, and is
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'DaRis91l MIr'l6sEnargy Puels.Resources (USA) ~Inc.
explicitly exempt from regulation under RCRA. It has also been classified as 11 e.(2) byproduct
material by NRC, and for this reason also is explicitly exempt from regulation under RCRA.
The Uranium Material has not been classified or treated as listed hazardous waste nor has it
been in contact with any listed hazardous wastes.
The RCRA analysis concluded that, based on the information that is available,
1. The Uranium Material is not a RCRA listed hazardous waste because it has been
classified by NRC as 11 e.(2) byproduct material and is therefore exempt from regulation
under RCRA.
2. Even if the Uranium Material had not been classified as 11 e.(2) byproduct material, the
Uranium Material would not be a RCRA listed hazardous waste because it is an ore that
has a natural uranium content of greater than 0.05 weight percent, is therefore source
material and, as a result, is exempt from regulation under RCRA.
3. Even if the Uranium Material were not 11 e.(2) byproduct material or source material, it
would not be a RCRA listed hazardous waste for the following additional reasons:
a) It was generated from a known process under the control of the generator, who has
provided an affidavit declaring that the Uranium Material is not and does not contain
RCRA listed hazardous waste. This determination is consistent with Boxes I and 2
and Decision Diamonds 1 and 2 in the DenisonEFRIlUDEQ Protocol Diagram;
b) The two volatile organic compounds detected at very low concentrations in the
Uranium Material have been attributed to laboratory contamination and are not actual
contaminants in the Uranium Material;
c) None of the metals in the Uranium Material samples came from RCRA listed
hazardous waste sources. This determination is consistent with Box 8 and Decision
Diamonds 9 through 11 in the DenisonEFRIlUDEQ Protocol Diagram.
4. The Uranium Material does not exhibit any of the RCRA characteristics of ignitability,
corrosivity, reactivity, or toxicity for any constituent.
3.3.4 Radioactive Material Profile Record
Furthermore, in order for Donison EFRI to characterize the Uranium Material, SFC has
completed Donison's EFRI's RMPR form, stating that the material is not RCRA listed waste. The
certification section of the RMPR includes the following text:
I certify that the material described in this profile has been fully characterized
and that hazardous constituents listed in 10 CFR 40 Appendix A Criterion 13
which are applicable to this material have been indicated on this form. I further
certify and warrant to Donison EFRI that the material represented on this form is
not a hazardous waste as identified by 40 CFR 261 and/or that this material is
exempt from RCRA regulation under 40 CFR 261.4(a)(4).
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3.3.5 Conclusion
Because the Uranium Material is 11 e.(2) byproduct material and/or is an ore that contains
greater than 0.05% source material, the Uranium Material is exempt from RCRA under 40 CFR
261.4(a)(4). In addition, based on the site history, the determinations by SFC, and the analysis of
the Denison's EFRI's chemical engineer, Denison EFRI has also concluded that, even if not
exempted from RCRA under 40 CFR 26104(a)(4), on the application of the Listed Hazardous
Waste Protocol, Uranium Material from the Facility would not be listed hazardous waste subject
to RCRA.
3.4 Uranium Material is Processed Primarily for its Source Material Content
In its Memorandum and Order, February 14, 2000, In the Matter of International Uranium (USA)
Corp. (Request for Materials License Amendment), Docket No. 40-8681-MLA-4, the NRC
concluded that an alternate feed material will be considered to be processed primarily for its
source material content if it is reasonable to conclude that uranium can be recovered from the
Uranium Material and that the processing will indeed occur. The Uranium Material will be
processed for the recovery of uranium at the Mill. Based on the uranium content of the Uranium
Material, its physical and chemical characteristics, and Denisen's EFRI's success in recovering
uranium from a variety of different types of materials, including materials that were similar to the
Uranium Materials, at the Mill, it is reasonable to expect that uranium can be recovered from the
Uranium Material. As a result, the Uranium Material is an ore that will be processed primarily for
the recovery of source material, and the tailings resulting from processing the Uranium Material
will therefore be 11 e.(2) byproduct material under the definition set out in 10CFR 4004.
4.0 ENVIRONMENT AFFECTED
4.1 General
The Mill is a licensed uranium proceSSing facility that has processed to date over 4,000,000 tons
of uranium-bearing conventionally mined ores and alternate feed materials primarily for the
recovery of uranium, with the resulting tailings being permanently disposed of as 11 e.(2)
byproduct material in the Mill's tailings impoundments. Environmental impacts associated with
such previously licensed Mill operations have been thoroughly evaluated and documented in the
past (see, for example, the original 1979 Final Environmental Statement ("FES") for the Mill,
Environmental Assessments ("EAs"), dated 1985 and 1997, an EA for the Mill's reclamation
plan dated 2000, EAs for alternate feed materials dated 2001 and 2002, in each case prepared
by the NRC, the Safety Evaluation Report for the Receipt, Storage and Processing of Fansteel
Alternate Feed Material prepared by DRC, and Safety Evaluation Reports prepared in
connection with the re-lining of tailings Cell 4A and construction of tailings Cell 4B.) The
Uranium Material will also be processed as an alternate feed at the Mill for the recovery of
uranium and the resulting tailings will be permanently disposed of in the Mill's tailings
impoundments as 11 e.(2) byproduct material, in a similar fashion to other conventionally mined
ores and alternate feed materials that have been processed or licensed for processing at the
Mill.
Accordingly, this Environmental Report will focus on the various pathways for potential
radiological and non-radiological impacts on public health, safety and the environment and
determine if the receipt and processing of the Uranium Material would result in any potential
significant incremental impacts over and above previously licensed activities.
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The pathways that are analyzed are the following:
a) potential impacts from transportation of the Uranium Material to the Mill;
b) potential impacts from radiation released from the Uranium Material while in
storage at the Mill;
c) any chemical reactions that may occur in the Mill's process;
d) any potential reactions or inconsistencies with the existing tailings or tailings
facilities;
e) potential impacts on groundwater;
f) potential impacts on surface water;
g) potential airborne radiologic impacts;
h) potential radon and gamma impacts; and
i) worker health and safety issues.
These potential pathways will be discussed in the following sections of this document. The
findings below will demonstrate that, because all the constituents in the Uranium Material have
either been reported to be, or can be assumed to be, already present in the Mill's tailings
system or were reported in other licensed alternate feeds, at levels generally comparable to or
higher than those reported in the Uranium Material, the resulting tailings will not be significantly
different from existing tailings at the facility. As a result, there will be no incremental public
health, safety or environmental impacts over and above previously licensed activities.
Processing of the Uranium Material involves no new construction, no additional use of land, no
modification of the Mill, main circuit, alternate feed circuit, or tailings system of any significance.
The Uranium Material contains no new chemical or radiological constituents beyond those
already processed in ores and approved alternate feeds, or already known or expected to be
present in the tailings system. As a result, there are no anticipated impacts to the environment
via any of the above pathways, above those already anticipated in the existing environmental
statements and environmental assessments associated with the Mill's approved license, which
have addressed:
• Geology and soils,
• Liquid effluents,
• Airborne effluents,
• Direct radiation,
• Management of sanitary wastes,
• Human and ecological receptor hazard assessment,
• Mill accidents,
• Transportation accidents,
• Groundwater impacts,
• Surface water impacts,
• Mill decommissioning,
• Land, structures, site and tailings reclamation,
• Internal inspection program,
• Corporate organization and management,
• Radiological protection training,
• Security,
• Quality assurance for all phases of the milling program,
• Operational effluent monitoring,
• Operational radiological monitoring,
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• Meteorological monitoring,
• Capacity of tailings system over the lifetime of the Mill operations,
• Permanent isolation of tailings including slope stability, settlement, and liquefaction
potential,
• Consideration of below-grade disposal of tailings,
• Tailings design requirements including site location and layout, site area, geography,
land use and demographic surveys, use of adjacent lands and waters, population
distribution, demography, meteorology, air models, geology and soils, seismology,
hydrologic description of the site, surface water, flooding determination, surface water
profiles, channel velocities, shear stresses, groundwater hydrology, radiological surveys,
site and uranium mill tailings characteristics, disposal cell cover engineering design, and
design of erosion protection covers,
• Groundwater protection standards,
• Liner construction,
• Prevention of overtopping,
• Dike design, construction, and maintenance,
• Cover and closure at end of operations including radon attenuation, gamma attenuation,
and cover radioactivity content,
• Effectiveness of final radon barrier including verification and reporting,
• Radium in cover materials,
• Radionuclides other than radium in soils,
• Non-radiological hazards,
• Completion of final radon barrier,
• Preoperational and operational monitoring programs,
• Effluent control during operations including gaseous and airborne particulates, liquids
and solids, contaminated equipment, sources and controls of Mill wastes and effluents,
sanitary and other Mill waste systems, effluents in the environment, effluent control
techniques, external radiation monitoring program, airborne radiation monitoring,
exposure calculations, bioassay program, contamination control program, airborne
effluent and environmental monitoring program, groundwater and surface water
monitoring program, control of windblown tailings and ore,
• Daily tailings inspections,
• Financial surety,
• Costs of long-term surveillance,
• Application for a groundwater discharge permit,
• Groundwater permit compliance monitoring,
• Background groundwater quality determination,
• Submission of data,
• Reporting of mechanical problems or discharge system failures,
• Correction of adverse effects, and
• Out of compliance status and procedures,
among other issues and requirements.
4.2 Transportation Considerations
4.2.1 Packaging and Mode of Transportation
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The Uranium Material from the Facility will be shipped by truck in SuperSaks of approximately
0.95 tons each, and approximately 21 bags per truckload. The bags will be shipped in truck
trailers with poly-lined bottoms and sides, either box-style trailers, or flatbed style trailers with
sidewalls and tarp covers. The Uranium Material will be shipped as Radioactive LSA I (low
specific activity) Hazardous Material as defined by DOT regulations. SFC will arrange with a
materials handling contractor for the proper marking, labeling, placarding, manifesting and
transport of each shipment of the Uranium Material. Shipments will be tracked by the shipping
company from the Facility until they reach the Mill. Each shipment will be "exclusive use" (i.e.,
the only material on each vehicle will be the Uranium Material). SFC will ship a total of
approximately 555 to 835 trucks over a period of 22 to 33 weeks, or an average of twenty five
trucks per week for 22 to 33 weeks, or 5 trucks per day based on 5 days of shipping per week.
The trucks involved in transporting the Uranium Material to the Mill site will be surveyed and
decontaminated, as necessary, prior to leaving the Facility for the Mill and again prior to leaving
the Mill site.
4.2.2 Transportation Impacts
For the following reasons, it is not expected that transportation impacts associated with the
movement of the Uranium Material by train and truck from the Facility to the Mill will be
significant:
a) Radiological Matters
The transport of radioactive materials is subject to limits on radiation dose rate measured at the
transport vehicle as specified in the US Code of Federal Regulations. The external radiation
standards for these shipments are specified in 10 CFR 71.47 sections (2) and (3) as less than
200 millirems per hour (Umremlh") at any point on the outer surface of the vehicle, and less than
1 0 mrem/h at any pOint two meters from the outer lateral surfaces of the vehicle. All exclusive
use trailer trucks will be scanned by SFC prior to departure from the Facility to ensure that these
limits are satisfied. From a radiologic standpoint, the Uranium Material is within the bounds of
other ores and alternate feed materials licensed for processing at the Mill. The Uranium Material
will be transported in covered exclusive use box-style or flatbed-style trailers, in a similar fashion
to other conventional ores, and as a result there will be no significant incremental radiological
impacts associated with transportation of Uranium Material to the Mill, over and above other
previously licensed ores and alternate feed materials at the Mill or from licensed activities at
other facilities in the State of Utah. An 80pHcabie reauiremenlS of 49 CFR Part 172 and Pari 173111i1l be mel.
and the selected transport company will have all !he requIred training and emergency response orograms and
certifications in place.
b) Traffic Volume Matters
(i) Comparison to Licensed Mi/I Operations
Section 4.8.5 of the 1979 FES for the Mill noted that during the operations period, when area
mining was at expected peak levels, approximately 68 round trips on local highways would be
made by 30-ton ore trucks to the Mill per day (see the 1978 Dames and Moore Environmental
Report for the Mill, p. 5-34). In contrast, approximately 25 truck loads per week (5 per day) will
be transported from the Facility to the Mill for a total period of approximately 22 to 33 weeks.
In addition, based on a licensed yellowcake capacity of 4,380 tons U30 S per year (Mill license
condition 10.1) a maximum of approximately 8,760,000 pounds of yellowcake would require
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QeAlseA-MiAe6Ef19trlv Fuels Flesources (USA) Geijllnc.
shipment from the Mill to conversion facilities. This would require approximately 183-275 truck
shipments from the Mill per year (based on 40-60 drums per truck, 800 Ibs per drum), or one
truck every one to two days based on a seven day work week (one truck every day or so, based
on a five-day work week). In contrast, the entire volume of yellowcake to be produced from
processing the Uranium Material is expected to be transported in a total of less than 8
truckloads. This frequency is minimal in comparison to the estimated yellowcake transport
frequency at licensed capacity. Moreover, during the period of transportation of the Uranium
Material to the Mill, GeAf&eA-EFRI does not expect that ore deliveries from all other sources
would, in total, exceed a small fraction of the truck transportation associated with licensed
capacity.
After leaving Gore, Oklahoma, the shipments will travel west via Interstate Highway 40, followed
by US and State Highways to the Four Corners area, to Utah State Highway (SH) 191 south of
Blanding and north on SH 191 to the Mill. The shipments will likely enter Utah via SH 262.
(ii) Comparison to Existing Truck Traffic on Utah State Highway 262
Based on information from the State of Utah Department of Transportation ("UDOT") traffic
analysis reports Traffic on Utah Highways 2009 and Truck Traffic on Utah Highways 2009,
accessed at the UDOT web page on October 30, 2010, on average during 2009, 103 multi-unit
trucks traveled west daily on SR262 to SR191. Based on the 2009 UDOT truck traffic
information, an average of five additional trucks per day traveling this route to the Mill during the
limited period anticipated for shipment of the Uranium Material represents an increased traffic
load of approximately five percent for that period. Therefore, the truck traffic to the Mill from this
project is expected to be an insignificant portion of existing truck traffic on SH 262 and well
within the level of truck traffic expected from normal Mill operations.
(iii) Comparison to Existing Truck Traffic on Utah State Highway 191
Based on information from the UDOT traffic analysis data, accessed at the UDOT web page on
October 30, 2010, on average during 2009, 292 multi-unit trucks traveled daily on SR 191 from
the Four Corners area to the Mill area south of Blanding. Based on the 2009 UDOT truck traffic
information, an average of 5 additional trucks per day traveling this route to the Mill during the
limited period anticipated for shipment of the Uranium Material represents an increased traffic
load of less than two percent for that period. As a result, the truck traffic to the Mill from this
project is expected to be an insignificant portion of existing truck traffic on SH 191, and well
within the level of truck traffic expected from normal Mill operations.
4.2.3 Transportation Accidents
As discussed in Section 2.3 and Attachment 5, the Uranium Material has a uranium content and
radioactivity levels comparable to Arizona Strip ores and previously-approved alternate feed
materials, and contains no additional constituents beyond those associated with other ores or
alternate feeds previously transported to the Mill. Therefore the Uranium Material poses no
additional hazards during transport above previously licensed activities. Existing accident
response and spill response procedures are therefore sufficient for management of potential
transportation accidents or spills of the Uranium Material.
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QeAiseti MlnesEnemy fuels Resources (USA) GeFttlnc.
4.3 Storage
4.3.1 Manner of Storage
Trucks arriving at the Mill site will be received according to existing Mill procedures. The
SuperSaks will be unloaded from the trucks onto the ore pad for temporary storage until the
material is scheduled for processing.
4.3.2 Environmental Impacts Associated With Storage
Because the Uranium Material does not significantly differ in radiological activity from other ores
and alternate feed materials, and because the Uranium Material will be stored in SuperSaks on
the Mill's ore pad pending processing, there will be no environmental impacts associated with
the Uranium Material over and above those associated with other ores and alternate feed
materials handled at the Mill on a routine basis. Experience at the Facility has determined that
the Uranium Material is stable under ambient environmental conditions and does not require
any special handling.
4.4 Process
The Uranium Material will be introduced to the process in the main circuit either alone or in
combination with other conventional ores or other alternate feeds. In either case, the material
will be processed through existing acid leach, counter-current decantation and solvent
extraction circuits for the recovery of uranium values. The leaching process will begin in Pulp
Storage with the addition of sulfuric acid. The solution will be advanced through the remainder
of the Mill or alternate feed circuit with no significant modifications to either the circuit or the
recovery process anticipated. The only wastes or effluents to be generated from processing the
Uranium Material are tailings solutions or solids to be transferred to the Mill's existing tailings
system.
Since no significant physical changes to the Mill circuit and no new process chemicals will be
necessary to process this Uranium Material, no significant construction impacts beyond those
previously assessed will be involved. Recovery of additional contained metals is not anticipated
at this time.
As with other alternate feed materials, a Standard Operating Procedure ("SOP") specific to
processing of the Uranium Material, addressing processing procedures, personnel safety and
radiation or other exposure monitoring will be developed and reviewed by the Mill's SERP, and
Mill personnel will be trained in the approved SOP prior to processing of the Uranium Material.
The effects of introducing the Uranium Material into the Mill's process and tailings were
reviewed by Denison's EFRI's chemical process engineer. The chemical engineer's Technical
Memorandum is included as Attachment 5. Table 5 in this Technical Memorandum provides
comparisons of the concentrations of all known constituents of the Uranium Material to the
tailings and other previously processed ores and alternate feeds. As discussed in Section 4.5
below, and in Attachment 5, the existing tailings system and tailings management controls are
adequate for management of any tailings generated from the Uranium Material.
_________________________________________________________________ P~age13
gef;iseM.4lnesEl1emy Fuels Resources (USA) ~Inc.
4.4.1 Mill Accidents and Emergency Response
As discussed in Section 2.3 and Attachment 5, the Uranium Material has a uranium content and
radioactivity levels comparable to Arizona Strip ores, and previously-approved alternate feed
materials, and contains no additional constituents beyond those associated with other ores or
alternate feeds previously transported to the Mill. Therefore the uranium Material poses no
additional hazards during storage, processing or disposal of tailings. As discussed in
Attachment 5, the Uranium Material will not introduce any new hazardous constituents, and
processing will not require the introduction of any new processing chemicals. Existing
emergency response and spill response procedures are therefore sufficient for management of
potential accidents or spills of the Uranium Material on the Mill site.
4.5 Compatibility with DeRis9R Mill Tailings
4.5.1 Physical Compatibility
The Uranium Material will be received as a dewatered sludge from filter press dewatering of
clarifier solids. A portion of this material may be insoluble in the acid leach process at the Mill,
and therefore the discharge sent to tailings may contain some solid material ("sand"). The
remainder of the Uranium Material will be soluble and will therefore be contained in the liquid
phase after processing in the acid leach system. The solids will be sent to one of the Mill's
active tailings cells (currently Cell 4A, or Cell 4B). The solutions from the Uranium Material
tailings will be recirculated through the mill process for reuse of the acidic properties in the
solution. The sands will be only a portion of the total mass of Uranium Material. However,
assuming a worst case scenario that all of the solid material ends up as sand in the tailings, it is
estimated that for the main processing circuit, the additional load to the tailings is minimal
(Attachment 5, Table 5). It is expected that the percent increase to the system is less than one
percent for all components.
Cell 4A, which has been in service since October of 2008, has received tailings solids and
solutions primarily from conventional ore processing together with a small volume from alternate
feed processing. Cell 4B, placed into service in February 2011 , will receive similar materials as
Cell 4A. Tailings from processing the Uranium Material may be transferred to either Cell 4A or
4B or comparable new cell. Both Cells 4A and 4B have similar primary and secondary high-
density polyethylene ("HDPE") flexible membrane liners, geosynthetic clay underliners, and
comparable leak detection system designs, selected specifically to meet current standards for
uranium mill tailings management.
The constituents in the tailings resulting from processing the Uranium Material are not expected
to be significantly different from those in the conventional ores either in composition or in
concentration of constituents. The Technical Memorandum on Worker Safety, Environmental
Issues and Chemical Compatibility (the "Safety and Compatibility Technical Memorandum",
Attachment 5) indicates that all of the constituents found in the Uranium Material have
previously been processed in the Mill's circuits and managed in the Mill's tailings system.
The Safety and Compatibility Technical Memorandum identified that the components of the
Uranium Material are not expected to have any adverse effect on the Mill processing system or
the tailings cells. As described in Attachment 5, it is expected that most of the metal and non-
metal impurities entering the leach system with the Uranium Material will be converted to sulfate
ions, precipitated, and eventually discharged to the tailings system.
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QeAisMMlMeErlergy' Fuels Rasources lUSAl Geft?lnc.
Every metal and non-metal cation and anion component in the Uranium Material already exists
or can be assumed to exist in the Mill's tailings system, is already addressed in the Mill's
groundwater monitoring program, or both. A summary of the anticipated tailings composition
before and after the Uranium Material is processed is presented in the Safety and Compatibility
Technical Memorandum Attachment 5.
Every identified component in the Uranium Material has been:
1. detected in analyses of the tailings cells liquids;
2. detected in analyses of tailings cells solids;
3. detected in analyses of alternate feed materials licensed for processing at the Mill; or
4. detected in process streams or intermediate products when previous alternate feeds
were processed at the Mill;
at concentrations that are generally comparable to the concentrations in the Uranium Material.
However, even if the Uranium Material were to contain some constituents at significantly higher
concentrations, due to the limited quantity of Uranium Material, any such increase in the
concentration of any analyte in the Mill's tailings would not be expected to be significant. The
estimated effect on tailings composition is discussed in the attached technical memorandum.
The constituents in the Uranium Material are expected to produce no incremental additional
environmental, health, or safety impacts in the Mill's tailings system beyond those produced by
the Mill's processing of natural ores or previously approved alternate feeds.
4.5.2 Capacity and Throughput
The amount of tailings that would potentially be generated from processing the Uranium
Material is equivalent to the volume that would be generated from processing an equivalent
volume of conventional ore. Processing of the Uranium Material will have no effect on the
capacity of the tailings system over the lifetime of the Mill operations beyond that of processing
a similar amount of natural ore. The Facility, as described above, may be expected to ship a
total of approximately 11 ,000 to 17,000 tons of Uranium Material to the Mill. This volume is well
within the maximum annual throughput rate and tailings generation rate for the Mill of 680,000
tons per year. Additionally, the design of the existing impoundments has previously been
approved by the NRC (Cell 3) and by the Utah DRC (Cells 4A and 4B), and Denisan EFRI is
required to conduct regular monitoring of the impoundment leak detection systems and of the
groundwater in the vicinity of the impoundments to detect any potential leakage should it occur.
4.5.3 Mill Tailings Closure and Reclamation
Processing of the Uranium Material will have no effects beyond those identified in the approved
ERs, ESs, Reclamation Plans from tailings operational management and closure. The Uranium
Material will have no effect on existing approved plans for decommiSSioning of the Mill,
buildings, land or structures, or reclamation of the site. The Uranium Material will have no effect
on tailings design components addressing permanent isolation of tailings, slope stability,
settlement or liquefaction of reclaimed tailings, or design features addressing disposal cell
covers or erosion protection.
Because radionuclide content is within the ranges associated with other ores and alternate
feeds approved for processing at the Mill, there will be no effect on radon attenuation, gamma
attenuation or cover radionuclide content. Because it will not affect cover design at closure and
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~Energv FUals Resollfces (USA) ~Inc.
reclamation, there will be no effect on the final radon barrier design or its method of
emplacement, radium concentration in cover materials, or other cover radionuclide content.
Processing of the Uranium Material will have no effect on completion of the final radon barrier or
on the timetable for completion of reclamation. Processing of the Uranium Material will not
require the acceptance of uranium byproduct material from other sources during closure.
Because processing the Uranium Material will have no effect on reclamation and closure
design, construction or timing, it will have no effect on existing and approved financial surety
estimates or arrangements, and will not require any changes to costs of long-term surveillance.
4.6 Groundwater
In the 1997 EA, NRC staff concluded that, for a number of reasons, groundwater beneath or in
the vicinity of the Mill site will not be adversely impacted by continued operation of the Mill.
Because the Mill's tailings cells are not impacting groundwater, the receipt and processing of
Uranium Material at the Mill will not have any incremental impacts on groundwater over and
above existing licensed operations.
Denisen EFRI meets the State of Utah Groundwater Protection Standards by complying with the
Mill's current Groundwater Discharge Permit ("GWDP"). The Mill initially applied for a GWDP in
2005. The current version was approved in .h,Ily--2G+t,August 2012. The primary groundwater
protection standard in UAC R313-24-4 is a design standard for surface impoundments used to
manage uranium and thorium byproduct material. The designs of the Mill's tailings Cells 4A and
4B, which will receive tailings from processing the Uranium Material, have been approved by
DRC as meeting Best Available Technology Requirements for the liners and other components
of the containment system.
The GWDP established points of groundwater monitoring compliance, a compliance monitoring
program, and agreed to the establishment of intra-well background for comparison with
groundwater compliance limits. The GWDP further established requirements for submission of
field and laboratory monitoring data, reporting of mechanical problems or discharge system
failures, correction of adverse effects, assessment of corrective actions, and notification,
reporting and procedures during any out-of-compliance status. Since the issuance of the initial
GWDP, the Mill has not sought to discontinue the GWDP.
All constituents identified in the Uranium Material, are already present or can be assumed to be
present in the Mill's tailings system, are already included in the Mill's groundwater monitoring
program, or both.
Chemical and radiological make-up of the Uranium Material is similar to other ores and alternate
feed materials processed at the Mill, and their resulting tailings will have the chemical
composition of typical uranium process tailings, for which the Mill's tailings system was
designed. As a result, the existing groundwater monitoring program at the Mill will be adequate
to detect any potential future impacts to groundwater.
As a result, there will be no incremental impacts over and above previously licensed activities.
4.7 Surface Water
There will be no discharge of Mill effluents to local surface waters. All Mill process effluents, and
analytical laboratory liquid wastes will be discharged to the Mill's tailings impoundments for
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~A&SEnernv Fuels Resources (USA) Ge$lnc.
disposal by evaporation. Runoff from the Mill and facilities is directed to the tailings
impoundments. Sanitary wastes are discharged to State-approved leach fields. Since there is
no plausible pathway for Uranium Material to impact surface water, and, as indicated in Semi-
Annual Effluent Reports filed by the Mill to date, there is no indication of the Mill impacting
surface waters, then there will be no incremental impact to surface waters from any airborne
particulates associated with processing the Uranium Material.
The Uranium Material will be transported to the Mill in closed SuperSaks in exclusive use trucks.
Upon introduction into the Mill circuit, the Uranium Material will be processed in a similar fashion
as other ores and alternate feed materials. The Uranium Material will be relatively moist, with an
average moisture content of approximately 55%. This will minimize any potential for dusting
while the Uranium Material is introduced into the Mill process. In addition, standard procedures
at the Mill for dust suppression will be employed if necessary. There will therefore be no new or
incremental risk of discharge to surface waters resulting from the receipt and processing of
Uranium Material at the Mill or the disposition of the resulting tailings.
Finally, as the chemical and radiological make-up of the Uranium Material are sufficiently similar
to natural ores and the tailings resulting #!efefrom them, tflat-the existing surface water
monitoring program at the Mill will be adequate to detect any potential impacts to surface water.
As a result, there will be no incremental impacts over and above previously licensed activities.
4.8 Airborne Radiological Impacts
The chemical and radiological make-up of the Uranium Material will not be significantly different
from natural ores and other alternate feeds that that have been licensed for processing at the
Mill in the past. The existing air particulate monitoring program is equipped to handle all such
ores and alternate feeds.
4.9 Radon and Gamma Impacts
As discussed in Section 2.5.2 above, the uranium content and radioactivity levels of the
Uranium Material is comparable to Arizona Strip breccia pipe ores and previously approved
alternate feed materials, except for thorium levels. which are discussed below. In fact, the Ra-
226 concentrations are in disequilibrium and much lower than even low grade Colorado Plateau
ores. Therefore, radon-22§Q emanations from the Uranium Material will be significantly lower
than from the same quantity of low grade ores. Also, the gamma fields from the U-nat chain are
derived primarily from R!!fI-226, which is very low. Therefore, the gamma from the U-nat chain
in the Uranium Material will be low. The lower gamma from the U-nat chain will be offset
somewhat from the Th-23ga chain radionuclides. However, this gamma is derived primarily
from the Th-228 in the Uranium Material, which is in disequilibrium and is low relative to its
parent Th-232. Overall, the Uranium Material will therefore pose a comparable or lower gamma
and radon hazard as other ores and alternate feed materials that have already been processed
or licensed for processing at the Mill.
Relative to mill operations. the gamma (adlalion and radon emissions from Uranium Material
delivered to the Mill in its existing form trom Sequoyah FlJels Is lower than Colorado Plateau
ore. The welgh/ed average concentration 01 Ra-226 In Seguoyah Fuels AF is reporled at 236'
pCf/g. For compar!sod. the B8-226 concentration from ·Colorado Plateau ores (0.25% UaOIl) Is
707 pCllg. Therefore. gamma radiation levels and radon (radQn-222) levels/both 01 which are
derived 'from the decay 01 Ra-226} In Uranium Material Is a laOlor of 3 lower lIian Colorado
Plateau ores.
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For gamma radiation [rom Ihe Ihonum In \118 Uranium Malerial. Ihe gamma radialia" dose f(om
Th"232 decay series is approximately '57 uSvlhr (using Ihe we ghted average concentration of
Th-232 (2.385 pCi/g) and assuming that Th-232 and Th-2-2B (and subsequent decay products)
are In equilibrium. For comparisorl. the gamma radialion dose Irom Ra-226.(using Ihe weighted
averagei eoncen!ratlon of Ra-226 (236 pCllg) is approxfmalely 3 uSv/hr. The gamma radiation
dose from Ihe Th-232 decay sWles in eaumbrlum In Ihe (lranlUm material from Seguoyah Fuels
is therefore about a factor 14 hiaher than that from the Ra-226 in the same material.
SFC has provided data indicating that the actual qamma liald from stored stacked Supersaks at
lha Gora facility.ls very low. A summary 01 available daia Is provided In Appendix B lo rhls
letter. The data indicated that the dose rates at the surface of the Supersaks were less than 1.6
mR/hr.
4.10 Safety Measures
4.10.1 General
During unloading of the Uranium Material SuperSaks onto the ore pad, while the Uranium
Material is being stored on the ore pad pending processing, while feeding Uranium Material into
the Mill process and while processing the Uranium Material and disposing of and managing the
resulting tailings, the Mill will follow existing Mill SOPs in addition to an SOP to be developed
specific to the Uranium Material, as discussed below.
4.10.2 Radiation Safety
a) Existing Radiation Protection Program at the Mill
The radiation safety program which exists at the Mill, pursuant to the conditions and provisions
of the Mill's Radioactive Materials License, and applicable State Regulations, is adequate to
ensure the protection of the worker and environment, and is consistent with the principle of
maintaining exposures of radiation to individual workers and to the general public to levels As
Low As Reasonably Achievable ("ALARA"). Employees YlIII~'I-pe_~
f*9{ae(.jva~~~11 faGe fosplraloF'6, if roqHf.r.e4--l-fl-al'lQitiefh-al\-worlmFS at tho Mill
are . ro~ulfOel 19 • ... ·s.ar 130f&OAal Ollltisally SIIR'lulat ~El LuFAiAElSGOASO ("OSL"~bad!1les or IRe
~i'lalenl to detest their Q)(pGSure lEI §aFRma-f-aEliat~
EFAI has preyiously deyeloped 8 specific SOP, appreved by lhe US NRC. for receipt,
unloading. stockpiling. proceSSing and tailings manaaement lor receipt. unloading. stockoillng.
Rmcesslng and 181llngs managemenl of alternate feed materialS with ereyaled levels of thorium.
The SOP. provided in Allachment . will be util zed for Ihe Uranium MateriaL
The primary hazards assoc !';lted with elevated thorium. are associated with alpha part culates
(assoclaled with Th-230). and gammaemanat.ion (from TI1·228 and 1h-232); wHich ara borh
addressed by measures included in lhe high Itlorium SOP. The SOP .cQntains Ihe following
Iyoes 01 additional protections:
• Measures 10 minImize dusting and airborne transport of paniellla'les from stQred
alternate feed -
Page 18
geJ:Il~Ene.!gv FlJels ResOufQes (USA) ~Inc.
• Measures to provide shielding. If reaulred. for gamma emanation. from stored alternate
feed
• Additional PPE
Additional area and breathing zone monitoring
• Maintaining of resulUng tamngs yoder solullon or soil cover, to minImize gamma
'emanallon, radon IIUx, and particulate dfspersiorl
b) Gamma Radiation
Gamma radiation levels associated with the Uranium Material are within levels of gamma
radiation associated with other ores and alternate feed materials processed or licensed for
processing at the Mill in the past. Gamma exposure to workers will be managed in accordance
with el(istfFl9 Mill standard oporating prooodl;lrasthe SOP for alternate feeds with elevated
thorium levels.
c) Radon
Radon levels associated with the Uranium Material are within levels of radon associated with
other ores and alternate feed materials processed or licensed for processing at the Mill in the
past. Radon exposures to workers will be managed in accordance with oxisting Mill standard
op~tatlA9 proGodLJrosthe modified SOP.
d) Control of Airborne Contamination
The Uranium Material is a fine-grained solid currenlly with an average moisture content of
approximately 55%. While stored on the ore pad, the uranium material will remain within the
SuperSaks used for transport. The Uranium Material will be stored in an area on the ore pad
separate from regular traffic and marked as Uranium Material. Additional provisIons of the SOP,
described above and In Attachment -7, will ba applied
Additional d9ust suppression techniques specified in the SOP. specifically covering and
moisture spraying -will be implemented, if roEll;lirod , while the Uranium Material is on the ore pad
and while it is being introduced into the Mill process, allRol;lgR IRis may bo I;lnnooossary dl;lo to
!M-~ati>Jely l'I~Alenl of IRe L!ra~ateffal . Once in the Mill process, the
Uranium Material will be in a dissolved form, and no special dust suppression procedures will be
required. As is the practice at the Mill for other alternate feed materials, the Derived Air
Concentration ("DAC") to be used in any analysis of airborne particulate exposure to workers
will be developed specifically for the Uranium Material, based on applicable regulations and Mill
procedures, in order to take into account the specific radionuclide make-up of the Uranium
Material. The Mill has safely received and processed alternate feed materials with comparable
concentrations of the radionuclides contained in the Uranium Material, under previous license
amendments, and can safely handle the Uranium Material in accordance with oxisting Mill
Slc!:AQarE! (l~'efa~~the specific Uranium Material SOP.
4.10.3 Occupational Safety
The primary focus of safety and environmental control measures will be to manage potential
exposures from radionuclide particulates. Response actions and control measures designed to
manage particulate radionuclide hazards will be more than sufficient to manage chemical
hazards from the metal oxides (see the conclusions of the Safety and Compatibility Technical
Memorandum in Attachment 5).
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~·MffieSEnergv Fuels Resou(<;es (USA) Ge$lnc.
4.10.4 Vehicle Scan
As stated in Section 4.2.1 above, the shipments of Uranium Material to and from the Mill will be
dedicated, exclusive loads. Radiation surveys and radiation levels consistent with applicable
DOT regulations will be applied to the exclusive use vehicles. For unrestricted use, radiation
levels will be in accordance with applicable values contained in the NRC Guidelines for
Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or
Termination of Licenses for Byproduct, Source, or Special Nuclear Material, U.S. NRC, May,
1987. If radiation levels indicate values in excess of the above limits, appropriate
decontamination procedures will be implemented.
4.11 Long Term Impacts
The Uranium Material is comprised of similar chemical and radiological components as already
exist in the Mill's tailings cells. Existing monitoring programs are therefore adequate and no new
monitoring procedures are required. As a result, there will be no decommissioning,
decontamination or reclamation impacts associated with processing the Uranium Material, over
and above previously licensed Mill operations.
4.12 Other Operational Considerations
Processing of the Uranium Material will not require changes to corporate organization or
administrative procedures, management control programs, management audit and inspection
programs, staffing levels or staff qualifications. Processing will not require modifications to the
Mill's existing security procedures.
4.13 Added Advantage of Recycling
SFC has expressed its preference for use of recycling and mineral recovery technologies for the
Uranium Material for three reasons: 1) for the environmental benefit of reclaiming valuable
minerals; 2) for the added benefit of reducing radioactive material disposal costs; and 3) for the
added benefit of minimizing or eliminating any long term contingent liability for the waste
materials generated during processing.
SFC has noted that the Mill has the technology necessary to process materials for the extraction
of uranium and to provide for disposal of the 11 e. (2) byproduct material, resulting from
processing primarily for the uranium, in the Mill's existing tailings impoundments. As a result,
SFC will contractually require Denison EFRI to recycle the Uranium Material at the Mill for the
recovery of uranium.
4.14 Consideration of Alternatives
This application is in response to a request by SFC for disposal/processing options in
connection with the clean-up of the Facility. The Mill is a facility that has been requested to
provide these services, because it is licensed to process materials for the recovery of uranium
and is licensed to create, possess and dispose of byproduct materials that are similar to the
Uranium Materials. Given that a decision to dispose of the Uranium Material at an offsite facility
is required, the only options are as to which offsite facility the Uranium Materials will ultimately
be sent for disposal. There are a limited number of facilities that are licensed to receive, store,
process or dispose of the Uranium Material. Alternatives to processing/disposal at the Mill would
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OeAw,oR MlnesEoerov Fuels Resources (USA) Geft1lnc.
be direct disposal or processing at one of these other facilities. If direct disposal is utilized, the
value of the recoverable uranium in the Uranium Material would not be realized.
Pag~
9sAlsaJ4.MiAesEMarqy Fuels Resources (USA) ~Inc.
5.0 CERTIFICATION
This application and Environmental Report has been submitted as of D060FABOr 2011 August
£~by
De~JlgmJ MI~JESENERGY FUELS RESOURCES (USA) GGRPINC.
By:
Page 22
ATTACHMENT 1
Sequoyah Fuels Corporation (SFC) Gore Facility Location
Figure 1:
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Facility Location Map
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Final RFI
ATTACHMENT 2
Radioactive Material Profile Record and Affidavit
Radioactive Material Profile Record
RADIOACTIVE MATERIAL PROFILE RECORD
Generator Name:, Seguoyah Fuels Corporation, Generator/Feed Stream #: .!..!n",o.!..!n,..e ___ ; Volume of Feed Material: 11000 cy (21000 ton)
Contractor Name: '-'n.:.o'-'ne=----_________ , Feed Stream Name: '-'n.:.on"'e"--____ , Delivery Date: to be determined
Check appropriate boxes: Licensed Y X N _ NORMINARM _; LLR W _; MW _: MW Treated _; MW Needing Trtmt _; DOE _; II e.(2) X;
Original Submission: Y _X_ N __ ; Revision #: .:..!n/""a>--_ Date of Revision: ...,n""/a"--___________ _
Name and Title of Person Completing Form: "'J""o.!..!h.!..!n-=E=.!I"'lis"-',-'P--'r""e"'s"->id.,e<.!.n'-'.t ________ , Phone: [phone], x226
A. CUSTOMER INFORMATlON:
GENERAL: Please read carefully and complete this form for one feed stream. This information will be used to determine how to properly
manage the material. Should there be any questions while completing this form, contact f~~"R \lffiofu!l;l'!.!-Y rlJ~' [k~ tll t,:,~ (USA)
~Inc. ("~EFRI") Environmental Management at 303.628.7798. MATERIALS CANNOT BE ACCEPTED AT DENISON'S EFRI'S
WHITE MESA MILL UNLESS THIS FORM IS COMPLETED. If a category does not apply, please indicate. This form must be updated
annually.
1. GENERATOR INFORMATION
EPA 10#: 110001224719 EPA Hazardous Waste Number(s) (if applicable): ..:..n""'/a"--___ _
Mailing Address: Sequoyah Fuels CorporatIon, P.O_ Bex 610, Gore, OK 74435
Phone: [phone] , Fax: [phone]
Location of Material (City, ST): .:::G""o'-'-r""e ..... , O=.;K'--_______ _
Generator Contact: ""J""ow,hw,n-"E;!.Ii""is"--____ Title: President
Mailing Address (if different from above): "'s ... a ..... m""e'--_____ _
Phone: ""sa""m'-'-'-"e'--______ , Fax: "'s=a:..:.m""e'--______ _
I B. MATERIAL PHYSICAL PROPERTIES (Should you have any questions while completing this section, contact DenisoH EFRI Environmental
Management at 303.628.7798.
l. PHYSICAL DATA (Indicate percentage of material that will pass through the following
grid sizes, e,g, 12" 100%,4" 96%,1" 74%,1/4" 50%,1/40" 30%,11200" .5%)
2. DESCRIPTION: Color rust BrownlMulti_ Odor mild Odorless_
Liquid_ SolidX Sludge_ Powder/Dust_
3. DENSITY RANGE: (Indicate dimensions) 1.34 -1.37
4. GENERAL CHARACTERISTICS (% OF EACH)
lb.lyd3
GRADATION OF
MATERIAL:
12" 100%
4" 100% -
1" _100%
1/4" _100%
1/40" -100%
11200" 97%
Soil zero Building Debris zero Rubble zero Pipe Scale zero Tailings ~ Process Residue _5_ Concrete zero Plastic/Resin zero
Other constituents and approximate % contribution of each: ....,n""o,,-t ""a""p""p""lic"'a..,b""le><-_____________ _
5. MOISTURE CONTENT: (For soil or soil-like materials).
(Use Std Proctor Method ASTM 0-698) Optimum Moisture Content: n/a %
A verage Moisture Content: 54.9 % (u and moisture on SOOth samples.xls)
Moisture Content Range: 22-77 %
6. DESCRIPTION OF MATERIAL (Please attach a description of the material with respect to its physical composition and characteristics.
This description can be attached separately or included with the attachment for Item D.l.) See Attachment 01.
Generator or Contractor Initials: _____ _
Page I of 4
Radioactive Material Profile Record: Sequoyah Fuels Corporation; dewatered raffinate sludge
C. RADIOLOGICAL EVALUATION
1. MATERIAL INFORMATION. For each radioactive isotope associated with the material, please list the following information.
Denison'sEFRI's license assumes daughter products to be present in equilibrium, these are not required to be listed below and do not
require manifesting. (Use additional copies of this form if necessary).
See Attachment 01 civ
Weighted Weighted
Isotopes Concentration Range Average Isotopes Concentration Range Average
(pCi/g) (pCi/g) (pCi/g) (pCi/g)
a. U-natural 4793 to 7041 5777 b. Th-230 43900 to 74400 55685
c. Ra-226 ~ to 367 236 d. Th-232 1060 to 4990 2385
e. Th-228 449 to 1110 699 f. to
ND -Analyte not detected.
All results are reported 011 a dry wei\;!ht basis
2. Y IBI I-the radioaClivitycolltaincd in the feed material Low-Level Radioactive Waste as defined in the Low-Level Radioactive Waste
Policy Amendments Act of 1985 or in DOE Order 5820.2A. Chapter III? (Please Circle) If yes, check "LLRW" block on line 3
of page 1.
3. ~ N LICENSED MATERIAL: Is the feed material listed or included on an active Nuclear Regulatory Commission or Agreement
State license? (Please Circle)
(If Yes) TYPE OF LICENSE: Source_X __ ; Special Nuclear Material __ ; By-Product __ ; Norm __ ; NARM __ ;
LICENSING AGENCY: U.S. Nuclear Regulatory CommIssion. License SU8-1Q10. Docket 40-8027
D. CHEMICAL AND HAZARDOUS CHARACTERISTICS
1. DESCRIPTION AND HISTORY OF MATERIAL
Please attach a description of the material to this profile. Include the following as applicable: The process by which the material was
generated. Available process knowledge of the material. The basis of hazardous material or waste determinations. A list of the chemicals
and materials used in or commingled with the material; a list of any and all applicable EPA Hazardous Waste Numbers, current or former;
and a list of any and all applicable land-disposal prohibition or hazardous-waste exclusions, extensions, exemptions, effective dates,
variances or deli stings. Attach the most recent or applicable analytical results of the material's hazardous-waste characteristics or
constituents. Attach any applicable analytical results involving the composition of the material. Attach any product information or
Material Safety Data Sheets associated with the material. If a category on this Material Profile Record does not apply, describe why it does
Was this material mixed, treated, neutralized, solidified, commingled, dried, or otherwise processed at any time after generation?
Dewatered with filter res
Y Has this material been transported or otherwise removed from the location or site where it was originally generated?
Y Was this material derived from (or is the material a residue of) the treatment, storage, and/or disposal of hazardous waste defined by
40 CFR 261?
Y IBI Has this material been treated at any time to meet any applicable treatment standards?
2. LIST ALL KNOWN AND POSSIBLE CHEMICAL COMPONENTS OR HAZARDOUS WASTE CHARACTERISTICS
(Y) (N) (Y) (N) (Y) (N)
a. ListedHW __ ....Ii..-b. "Derived-From" HW __ ....Ii..-c. Toxic __ ....Ii..-
d. Cyanides --.li-e. Sulfides __ ....Ii..-f. Dioxins --....Ii..-
g. Pesticides __ .li-h. Herbicides __ ....Ii..-i. PCBs --~
j. Explosives --~ k. Pyrophorics __ ....Ii..-I. Solvents __ ....Ii..-
m. Organics __ ....Ii..-n. Phenolics __ ....Ii..-o. Infectious __ ....Ii..-
p. Ignitable ___ N_ q. Corrosive ___ N _ r. Reactive -----.tL..
s. Antimony -Y--t. Beryllium -Y---u. Copper -Y---
v. Nickel -Y---w. Thallium -Y---x. Vanadium __ ....Ii..-
y. Alcohols __ ....Ii..-z. Arsenic -Y--aa. Barium -Y---
bb. Cadmium __ ....Ii..-cc. Chromium -Y--dd. Lead -Y---
ee. Mercury -Y---ff. Selenium -Y--gg. Silver -_ ....Ii..-
hh. Benzene __ ....Ii..-ii. Nitrate -Y--jj. Nitrite -_ ....Ii..-
kk. Fluoride --L-_ II. Oil __ ....Ii..-mm.Fuel __ ....Ii..-
nn. Chelating Agents ___ N_ 00. Residue from water treatment __ ---.l:i-
pp. Other Known or Possible Materials or Chemicals: None.
Generator or Contractor Initials: _____ _
Page 2 of 4
Radioactive Material Profile Record: Sequoyah Fuels Corporation; dewatered raffinate sludge
Generator or Contractor Initials: _____ _
3. ANALYTICAL RESULTS FOR TOXICITY CHARACTERISTICS.
(Please transcribe results on the blank spaces provided. Attach additional sheets if needed, indicate range or worst-case results).
See Attachmel l 01 ! Tab! S 1 and 2 an I All chments D.1cii, D.1ciii. and D.l evl
Metals (circle one): Total (mg/kg) or TCLP (mg/I) Organics :Tolal (mg/kg) -See Table 2 and Attachment D.l cii
Arsenic 3030 0.097
Barium 4150 <0.098
Cadmium 1.03 <0.100
Chromium 605 0.202
Mercury 1.76 0.0003
Lead 10 10 <0. 100
Selenium 348 <0.140
Silver <1.00 0.238
ANALYTICAL RESULTS FOR REQUIRED PARAMETERS:
(Please transcribe results on the blank spaces provided. Attached additional sheets if needed).
SoilpH~ Paint Filter No Free Liquid Pass
Liquids Test (Pass/Fail)
5. IGNITABILITY (40 CFR 261.21[a][2].[4].)
Flash Point not appticable
4. CHEMICAL COMPOSITION
Cyanide n/a Not detected Sulfide n/a Not detected
Released mg/kg Released mg/kg
Is the material a RCRA oxidizer? Y 181
(List all known chemical components and circle the applicable concentration dimensions. Use attachments to complete, if necessary.)
See Attachment 01! tTables 1 ,-and 2. and 5. and Attachments 0_ 1 eli through 0 .1 eve All resulls are repOlle on a drY
weight basis.
Chemical Component Concentration
___ 0/ rng(kg
___ 9'1 mg/kg
___ %mglkg
Chemical Component Concentration
_____________ % mg/kg
_____________ % mg/kg
_____________ % mg/kg
Halogenated Organic Compounds (HOC) (Sum of the list of HOCs) mg/kg
E. REQUIRED CHEMICAL LABORATORY ANALYSIS. Generator must submit results of analyses of samples of the material. Results are
required from a qualified laboratory for the following analytical parameters unless nonapplicability of the analysis for the material can be stated
and justified in attached statements. Attach all analytical results and QAlQC documentation available. (CAUTION: PRIOR TO ARRANGING
FOR LABORATORY ANALYSIS, CHECK WITH DENISON EFR I AND LABORATORY REGARDING UTAH LABORATORY
CERTIFICATIONS.)
FOR ALL MATERIAL TYPES: CHEMICAL ANALYSIS: Soil pH (9045), Paint Filter Liquids Test (9095), Reactivity (cyanide and sulfide).
1. MINIMUM ADDITIONAL ANALYTICAL REQUIRED FOR:
a. Non-RCRA Waste (Non Mixed Waste e.g., LLRW, NORM): TCLP including the 32 organics, 8 metals, and copper (Cu) and zinc
(Zn).
2. REQUIRED RADIOLOGICAL ANALYSES. Please obtain sufficient samples to adequately determine a range and weighted average of
activity in the material. Have a sufficient number of samples analyzed by gamma spectral analysis for all natural isotopes such that they
support the range and weighted average information for the material that will be recorded in item D.I. If Uranium, Thorium, or other non-
gamma emitting nuclides are present in the material, have at least (1) sample evaluated by radiochemistry to determine the concentration of
these additional contaminants in the material.
See Attachment D1 civ.
Generator or Contractor Initials: _____ _
Page 3 of 4
3. PRE-SHIPMENT SAMPLES OF MATERIAL TO DENISONEFRI
Once permission has been obtained from -Dettiffit!EFRl, and unless amenability samples have previously been sent to ~EFRI, please
send 5 representative samples of the material to ~EFRI. A completed chain of custody form must be included with the sampling
containers. These samples will be used to establish the material's incoming shipment acceptance parameter tolerances and may be
analyzed for additional parameters. Send about two pounds (one liter) for each sample in an air-tight clean glass container via United
Parcel Post (UPS) or Federal Express to:
l+.ffii·StHl.-Mtlte-rt-llltA·Lh1f1 Enllf'l) Fud~ Rc~l\un:\!S t1 ISA. hle' .. , Attn: Sample Control, 6425 S. Highway 191, P.O. Box 809, Blanding,
UT 84511 Phone: [phone]
4. LABORATORY CERTIFICATION INFORMATION. Please indicate below which of the following categories applies to your laboratory
data.
a. All radiologic data used to support the data in item c.1. must be from a certified laboratory.
__ UTAH CERTIFIED. The laboratory holds a current certification for the applicable chemical or radiological parameters from the Utah
Department of Health insofar as such official certifications are given.
---X-GENERATOR'S STATE CERTIFICATION. The laboratory holds a current certification for the applicable chemical parameters
from the generator's State insofar as such official certifications are given, or
See Attachment E4a
• New Jersey Department of Environmental Protection, National Environmental Laboratory Accreditation Program,
Annual Certified Parameter List and Current Status, Outreach Laboratory, and
• Oklahoma Department of Environmental Quality, Laboratory Accreditation Program, Outreach Laboratory.
__ GENERATOR'S STATE LABORATORY REQUIREMENTS. The laboratory meets the requirements of the generator's State or
cognizant agency for chemical laboratories, or:
b. For analytical work done by Utah-certified laboratories, please provide a copy of the laboratory's current certification letter for each
parameter analyzed and each method used for analyses required by this form.
c. For analytical work done by laboratories which are not Utah-Certified, please provide the following information:
David Caldwell
State or Other Agency Contact Person
Donna Eidson
Lab Contact Person
F. CERTIFICATION
OK
Generator's State
OK
Laboratory's State
405-702-1024
Telephone Number
918-251-2515
Telephone Number
GENERATOR'S CERTIFICATION: I also certify that where necessary those representative samples were or shall be provided to ~
EFRI and to qualified laboratories for the analytical results reported herein. I also certify that the information provided on this form is complete,
true and cotTect and is accurately supported and documented by any laboratory testing as required by -Dettiffit!EFRI. I certify that the results of
any said testing have been submitted to -Dettiffit!EFRI. I certify that the material described in this profile has been fully characterized and that
hazardous constituents listed in 10 CFR 40 Appendix A Criterion 13 which are applicable to this material have been indicated on this form. I
further certify and warrant to Denison EFRl that the material represented on this form is not a hazardous waste as defined by 40 CFR 261 and/or
that this material is exempt from RCRA regulation under 40 CFR 261.4(a)(4).
The Generator's responsibilities with respect to the material described in this form are for policy, programmatic, funding and scheduling
decisions, as well as general oversight. The Contractor's responsibilities with respect to this material are for the day-to-day operations (in
accordance with general directions given by the Generator as part of its general oversight responsibility), including but not limited to the
following responsibilities: material characterization, analysis and handling; sampling; monitoring; record keeping; reporting and contingency
planning. Accordingly, the Contractor has the requisite knowledge and authority to sign this certification on behalf of itself, and as agent for the
Generator, on behalf of the Generator. By signing this certification, the Contractor is signing on its own behalf and on behalf of the Generator.
Generator's or Contractor's Signature
(Sign for the above certifications).
______________ Title President
Print Name of Individual Signing above: ... J,..oh""n"-'...H!.!., . ....,E""II""is'--______ _
Page 4 of 4
Date _____ _
Signed Affidavit
AFFIDA VIT OF JOHN H. ELLIS
I, John H. Ellis, being duly sworn according to law, depose and state as follows:
1. I am presently employed as the President for Sequoyah Fuels Corporation
("SFC") at the company's Gore, Oklahoma facility. In that capacity I am responsible for
senior project management oversight for implementation and execution of reclamation
activities at SFC's Gore facility, operation of facility equipment and systems,
implementation and oversight of decommissioning activities, and related activities
including waste management. My experience with SFC dates back to 1992 when I was
first employed at the company's Gore, Oklahoma facility. I have personal knowledge of
the raw materials used, the production processes employed, and the waste handling
procedures followed at SFC's Gore facility.
2. SFC proposes to ship to Energy Fuels Resources (USA) Inc.: White Mesa
Mill in Blanding Utah, the following material: dewatered raffinate sludge, for processing
as alternate feed materials. All of the proposed alternate feed materials are secondary
products or waste streams produced in the conversion of uranium or the decommissioning
of uranium conversion equipment at facilities owned and operated by SFC, and contains
no materials or wastes from any other source.
3. The raffinate sludge consists of precipitated and settled soil, rock particles,
metals, and radionuclides removed from the yellowcake feed (uranium) during the
purification process at the SFC facility. No wastes from any other source are combined
with the raffinate sludge. The raffinate sludge was passed through a filter press to
remove water thus creating the dewatered raffinate sludge.
AFFIDA VIT OF JOHN H. ELLIS (continued)
4. I have reviewed and am familiar with the Utah Hazardous and Solid Waste
Regulations R315-2-10 and R315-2-11 and the Code of Federal Regulations Title 40
Section 261.31 through 33 (the "Regulations") in the fonn attached hereto as Exhibit A.
Based on the processing steps employed in SFC's uranium conversion facility, the
proposed alternate feed materials do not contain any of the listed wastes enumerated in
the Regulations.
5. Based on my knowledge of waste management at SFC's facilities, the
proposed alternate feed materials have not been mixed with wastes from any other source,
which may have been defined as or which may have contained listed wastes enumerated
in the Regulations.
6. Specifically, the proposed alternate feed materials do not contain
hazardous wastes from non-specific sources (Utah RCRA F type wastes) because (a)
SFC does not operate any processes which produce the types of wastes listed in Section
261.31 of Title 40 of the Regulations, and (b) SFC has never accepted, nor have the
proposed alternate feed materials ever been combined with, wastes from any other source
which contain Utah RCRA F type wastes as defined therein.
7. Specifically, the proposed alternate feed materials do not contain
hazardous wastes from specific sources (Utah. RCRA K type wastes) because SFC does
not operate any of the processes which produce the types of wastes listed in Section
261.32 of Title 40 of the Regulations, and (b) SFC has never accepted, nor have the
proposed alternate feed materials ever been combined with, wastes from any other source
which contain Utah RCRA K type wastes as defined therein.
AFFIDA VIT OF JOHN H. ELLIS (continued)
8. Specifically, the proposed alternate feed materials are not Utah RCRA P or
U type wastes as defined in Section 261.33 of Title 40 of the Regulations because they (a)
are not manufactured or formulated commercially pure grade chemicals, off spec
commercial chemical products or manufacturing chemical intermediates, residues from
containers that held commercial chemical products or manufacturing chemical
intermediates, or any residue or contaminated soil, water or other debris resulting from a
spill cleanup, and (b) SFC has never accepted, nor have the proposed alternate feed
materials ever been combined with, wastes from any other source which contain Utah
RCRA P or U type wastes as defined therein.
th
Dated the 30 day of :r .... tff
Sworn to and subscribed before me
this 30~y of~, 2013
Notary Public
My Commission Expires:
,2013 /#t~M~ r John H. Ellis
RMPR Attachment 0.1
Radioactive Material Profile Record: Sequoyah Fuels Corporation; dewatered raffinate sludge
D. CHEMICAL AND HAZARDOUS CHARACTERISTICS
1. DESCRIPTION AND HISTORY OF MATERIAL
a. The process by which the material was generated.:.
Sequoyah Fuels Corporation chemically converted uranium ore concentrates to uranium
hexafluoride. This process included two primary purification steps: digestion followed by
solvent extraction. Digestion occurred by dissolving the uranium in nitric acid. The resulting
slurry was subjected to solvent extraction using tributyl phosphate diluted with n-hexane.
Process conditions were controlled to extract uranium into the organic phase. The milling
impurities remain in the aqueous phase, a dilute nitric acid mixture termed raffinate.
The aqueous raffinate stream is primarily a solution of nitric acid, metallic salts, and trace
quantities of uranium and radioactive transformation products of natural uranium, primarily
Th-230 and Ra-226. The aqueous raffinate stream was combined with spent sodium
hydroxide from nitrous oxide scrubber systems and waste sodium carbonate solutions. The
untreated raffinate stream from solvent extraction was pumped to an impoundment and
allowed to cool. Anhydrous ammonia was added to the raffinate solution to convert the dilute
nitric acid to ammonium nitrate. The addition of the anhydrous ammonia also increased the
pH of the raffinate solution causing the metallic salts and trace quantities of uranium, thorium,
and radium to precipitate and settle out in the impoundments as raffinate sludge. The treated
raffinate solution was decanted to another impoundment for further treatment with barium
chloride to remove trace levels of radium through co-precipitation. This precipitate was
periodically combined with the raffinate sludge in the other impoundments.
The raffinate sludge was transferred by slurry to other storage ponds as necessary. The final
treated raffinate solution was stored in surface impoundments prior to use as an ammonium
nitrate fertilizer.
b. Available process knowledge of the material.
The raffinate sludge was accumulated and stored in several impoundments on site, including
Clarifier A basins and Pond 4. No other materials were combined with the stored sludge.
The raffinate sludge was eventually consolidated to Clarifier A basins to support
decommissioning Pond 4 and dewatering of the raffinate sludge.
The raffinate sludge was slurried from Clarifier A basins and processed through a 225 psi
filter press to remove entrained water. The dewatered sludge was placed in one cubic yard
polypropylene bags. The bags are stored on site.
Page 1 of 5
sfc rmpr dewatered sludge d1 .doc February 2010
Radioactive Material Profile Record: Sequoyah Fuels Corporation; dew ate red raffinate sludge
D. CHEMICAL AND HAZARDOUS CHARACTERISTICS
1. DESCRIPTION AND HISTORY OF MATERIAL
c. The basis of hazardous material or waste determinations.
Physical and chemical properties of the raffinate sludge have been determined at different
times to support site characterization activities and treatability studies. The results of those
determinations are described in the RCRA Facility Investigation Report (RFI) and the Site
Characterization Report (SCR): information from these reports is summarized below.
Assessment of the data provided in the RFI or the SCR is included in the respective report.
Information regarding physical and chemical properties of the raffinate sludge developed in
support of evaluating dewatering the sludge is also summarized here.
F-e1:lF-6ample-&-'o'Ief&«)!fef;,,*Hn-Mar-Gll4994-from -P~I-1{J-4-JeF-tI:I& f*lfF1GS -Gk:ielermininy
OOAGafltrotions of-mf+tal.s..aAd"faGiGmJGlu:Jes .. jH .. .fhe-ralfH=la4e-&k:!fJ§er#lEHWera e~aAal~ I . ~
feStlUs-ef-tfteoe-samp!os-ara presonted In TabK7-l-a6-f.l.aw-$lue'ge.-A-tlempG&ite-sample was
aevelt>f3e~ e-samplcs fOF lfle-f.lllijQQse-eklelleGliHy-a-lea~l'lat ~ 'he-aAa ytleal-r*ults
ef--l..he-leashat-€--a fe-j~:eseAwd IA Tabl~h-Jgge-l:eacRate-:
The raffinate sludge in Pond 4 was transferred to Clarifier A basins between 1993 and 1995.
A single sample of raffinate sludge was collected from basin 1 of Clarifier A in January 1995
to determine the concentration of volatile and semivolatile organic compounds; the basis for
the selection of constituents is provided as Attachment D1 ci. The analytical results of this
sample are-that are greater than respective method detection limit are presented in Table 2.
The results presented in Table 2 are for sludge that had not been subjected to dewatering.
The laboratory report of results for each constituent for this sample is provided as Attachment
D1cii.
Raffinate sludge was collected in May 2003 from basin 1 of Clarifier A for the purpose of
testing feasibility of dewatering the raffinate sludge using a pressurized plate filter press.
After dewatering by the filter press, three samples were developed and analyzed for metals
and radionuclides. The three samples included the dewatered sludge, the water expelled
from the sludge as a result of dewatering (filtrate), and a leachate derived from the dewatered
sludge. The analytical results of these samples are presented in Table 1 as Dewatered
Sludge Mav 2003 Total Metals. and, In Table 5 as Dewatering Fif(rate;-aAG-f)ewaleFeEJ
SltJdge Leachate, respectively. The laboratory reports for these samples are provided as
Attachment D1 ciii.
Physical characteristics of the raffinate sludge are provided in tables 3 and 4. These results
represent the raffinate sludge before and after dewatering by pressurized plate filter press,
respectively. The dewatered sludge passes the paint filter test for free liquids (EPA Method
9095A).
Dewaterecl raffinate sludae samules were collected in December 2012 and analyzed for lotal
metals and I oxicity Characteristic Leachate Procedure ("TCLP") metals. The analytical suite
of metals are based on 40 CFR 261.24 Table 1 Maximum Concnetration of Contaminanats
for the Toxicity Characteristic. The analytical results are summarized in Table 1 as the
Dewsfered Sludge December 20 12 -Total Metals and DeVllalered Sludae TCLP Let:lC/1ale
December 2012 respectively. The laboratory renort for the December 201 2 analysis is
included as Attachement D.1 cv.
Page 2 of 5
sfc rmpr dewatered sludge d1.doc February 2010
Radioactive Material Profile Record: Sequoyah Fuels Corporation; dewatered raffinate sludge
D. CHEMICAL AND HAZARDOUS CHARACTERISTICS
1. DESCRIPTION AND HISTORY OF MATERIAL
A li st of the chemicals and materials used in or commingled with the material; a list of any and all
applicable EPA Hazardous Waste Numbers, current or former; and a list of any and all applicable land-
disposal prohibition or hazardous-waste exclusions. cxtcn ions. eXel11'pLimlS, effective dare-s, vatiance.~
or delistings. -
Chemicals or materials used in or comingled with the raffinate sludge.
• nitric acid
• tributyl phosphate
• n-hexane
• anhydrous ammonia
• barium chloride
• spent sodium hydroxide
• waste carbonate solutions
• recovered weak acids
Any and all applicable EPA Hazardous Waste Numbers
• none
Any and all applicable land-disposal prohibition or hazardous-waste exclusions, extensions,
exemptions, effective dates, variances or delistings
• none
d. Attach the most recent or applicable analytical results of the material's hazardous-waste characteristics
or constituents.
See attachments 01 cii a-RG--throlJqh 01 cym for applicable laboratory reports.
e. Attach any Hpolicable analylic:al results-in olvlnl! the comp 'si li Ii of lhe material.
None
f. Attach any product information or Material Safety Data Sheets associated with the material.
None
Page 3 of 5
sfc rmpr dewatered sludge d1.doc February 2010
Radioactive Material Profile Record: Sequoyah Fuels Corporation; Dewatered Raffinate Sludge
D. Chemical and Hazardous Characteristics
1. Description and History of Material
a e T bl 1 S ummary 0 Iytica a f Anal • I D ta
Dewatered Dewatered Dewatered TCLP
Sludgeb Sludge Sludge Regulatory
TCLP Leveld
Parametera May 2003-Decemberc
LeachateC
Total 2012 -December Metals Total Metals 2012 ......,
Ag <90.8 mg/kg <1.00 mg/kg 0.238 mg/l 5.0 mg/l
Al 160000 mg/kg No Analysis No Analysis -
As 3030 mg/kg 1280 mg/kg 0.097 mg/l 5.0 mg/l
Ba 4150 mg/kg 1530 mg/kg <0.098 100 mg/l
Be 18.7 mg/kg No Analysis No Analysis -
Ca 114000 mg/kg No Analysis No Analysis -
Cd <267 mg/kg 1.03 mg/kg <0.100 1.0 mg/l
Co 133 mg/kg No Analysis No Analysis -
Cr 605 mg/kg 251 mg/kg 0.202 5.0 mg/l
Cu 2360 mg/kg No Analysis No Analysis --
Fe 164000 mg/kg No Analysis No Analysis ---
I
Hg * 1.76 mg/kg 0.0003 mg/l 0.2 mg/l
K 7740 mg/kg No Analysis No Analysis
Li <2.67 mg/kg No Analysis No Analysis -
Mg 7190 mg/kg No Analysis No Analysis -
Mn 1930 mg/kg No Analysis No Analysis -
Mo 10700 mg/kg No Analysis No Analysis -
Na 7480 mg/kg No Analysis No Analysis -
Ni 1660 mg/kg No Analysis No Analysis -
P 19600 mg/kg No Analysis No Analysis -
Pb 1010 mg/kg 361 mg/kg <0.100 5.0 mg/l
Sb 78.4 mg/kg No Analysis No Analysis -
Se 348 mg/kg 97.9 mg/kg <0.140 1.0 mg/l
Sr 1210 mg/kg No Analysis No Analysis -
TI 5860 mg/kg No Analysis No Analysis -
V <1.60 mg/kg No Analysis No Analysis -.--
Zn <751 mg/kg No Analysis No Analysis --
U-total 19400 [lg/g No Analysis No Analysis -
Th-230 16200 pCi/g No Analysis No Analysis ---
Ra-226 219 pCi/g No Analysis No Analysis -
a Metals by EPA Method 6010; Mercury by 747017471 ; Ra-226 by SM7500 Ra (M); Tb-230 by LANL ER200 M; u by ASTM
5174 M
b Sample ID MISC raff-filter press only, May 2003 [CoC SF03-278]
C Sample ID SD-282, December 2012
d 40 CFR 261.24, Table 1 -Maximum Concentration of Contaminants for the Toxicity Characteristic.
Page 4 of 5
* Data for this analysis will not be used due to exceedance of the EPA holding time. Data from the Total Metals analysis
conducted in December 2012 will be used for assessment purposes.
Table 2 SURlllUlry of Organic and Mercury ADalyses of Raffinate Siudgell
Parameter Value Comment
Mercury (totalt . 0.34 mg/kg Practical quantitation limit 0.01 mg/kg
VolatileC 2-Butanone, 0.3 mg/kg Practical quantitation limit 0.1 mg/kg
2-Hexanone, 0.08 mg/kg Practical quantitation limit 0.05 mg/kg
SemivolatileO None . Not Applicable.
.• Sample ID SDOI4, January 1995 [Cham-of-Custody E-0131-95]
~EPAMethod 7471
• EPA Method 8240
d EPA Method 8270
T bl 3 Ph . I Ch a e IYSlca 'f aracterIS ICS 0 fR ffi SI d a mate . u Ige
Parameter Value Comment
Density 1.17 glcm.:l One measurement made on site May 2003.
% Solids 18% A calculated value form data collected May 2003.
Table 4 Physical Characteristics of Raffinate Sludge After Dewatering Using the Filter
Press
Parameter Value Comment
Density 1.36 g/cmj Average of four measurements made on site in May 2003.
% Solids 45% Average of four measurements made on site in May 2003.
% Weight 46% Average of four measurem nts made on site in May 2003.
Reduction
Load Bearing 41.71b/in2 Unconfined compressive strength with penetrometer May
2003.
Weight Per Max 2200 lb. The rated weight capacity of the package.
Package The package is 3'X3"X4" polypropylene sack.
Table 5 Anion Data for Dewatered Raffinate Sludge
Dewatered
Parameter Raffinate
Sludgea
F 44,100 mg/kg
N03(N) 4,580 mg/kg
NH3(N) 5,210 mg/kg
" Sample ID SD282, July 2013 -reported on a dry-weight basis
Page 5 of 5
RMPR Attachment 0.1 ci
Radioactive Material Profile Record: Sequoyah Fuels Corporation; dewatered raffinate sludge
D. CHEMICAL AND HAZARDOUS CHARACTERISTICS
1. DESCRIPTION AND HISTORY OF MATERIAL
c. The basis of hazardous material or waste determinations.
Attachment Dici
Basis for the Selection of Constituents I
The RCRA Facility Investigation required contamination
characterization for those constituents found in 40 CFR Part 261
Appendix VIII and Part 264 Appendix IX.
SFC identified potential Appendix VIII and Appendix IX
contaminants at the Site utilizing EPA's RFI guidance document
(EPA 530/SW-89-031), herein referred to as the guidance
document. Specifically, List 4 (Industry Specific Monitoring
Constituents) of Volume 1 of the guidance document indicated
those constituents which may be present at a site based on the
site's particular industrial classification.
Samples specified in the RFI Workplan for comprehensive analysis
were analyzed for those Appendix VIII and Appendix IX
constituents specified in the guidance document for the mining
industry, the inorganic chemicals industry and the non-ferrous
metals industry, with the following exceptions:
• Metals analysis conducted by Method 6010 (SW-846) provided
results for two (2) additional metals which are not listed
in the guidance document. The two metals (calcium and
molybdenum) were included based on their potential presence
in some of the Site process materials.
1 Sequoyah Fuels Corporation, Final RCRA Facility Investigation Workplan, Section 1.5.4 Comprehensive List of
Constituents, October 31 , 1994 (Revised January 4, 1995).
Page I of9
sfc rmpr dewatered sludge d1cLdoc February 2010
Radioactive Material Profile Record: Sequoyah Fuels Corporation; dewatered raffinate sludge
D. CHEMICAL AND HAZARDOUS CHARACTERISTICS
1. DESCRIPTION AND HISTORY OF MATERIAL
c. The basis of hazardous material or waste determinations.
Attachment DIci
• Analysis was not provided for the organochlorine pesticides
listed in Table 2-8. Pesticides at the Facility were
applied only as a function of their intended use. No
reports of pesticide spills were revealed through Facility
records or employee interviews. Storage of pesticides was
in the original container with no facility available for
bulk storage. Therefore, residual pesticide levels found
in Facility soils would be a result of standard practices
for pesticide usage.
• Four constituents listed in both 40 CFR Appendix VIII and
in the guidance document are not normally included in the
results for the analytical methods being utilized for the
RFI. A review of the four constituents was conducted, and
a determination made, that none of the four (7-H-
dibenzo(c,g) carbazole, dibenzo(a,h)pyrene,
dibenzo(a,i)pyrene and chloroacetaldehyde) have the
potential to be present at the Facility. This
determination was based on the fact that none of the four
constituents have been associated either directly or
indirectly with Facility processes, nor are any of the four
potentially present from the breakdown of chemicals which
were associated with the process.
Page 2 of9
sic rmpr dewatered sludge d1cLdoc February 2010
Radioactive Material Profile Record: Sequoyah Fuels Corporation; dewatered raffinate sludge
D. CHEMICAL AND HAZARDOUS CHARACTERISTICS
1. DESCRIPTION AND HISTORY OF MATERIAL
c. The basis of hazardous material or waste determinations.
Attachment Dlci
The constituents associated with the three types of industries
referenced above are listed in the guidance document in Tables
2 -1, 2 -2, 2 -3, 2 -4, 2 -6, 2 -8, 2 - 1 0, 2 -11, 2 -13, 2 -14 and 2 -15
and are shown in Table 3 of the RCRA Facility Investigation
(RFI) Workplan and included below. Table 3 lists the organic
and inorganic constituents included, as well as those to be
excluded, from the results for samples subjected to
comprehensive analysis in SFC's RFI Report. Those constituents
which were not included in the RFI Report are identified in the
table. This comprehensive list of constituents was analyzed by
utilizing Methods 6010 (metals), 7470 and 7471 (aqueous and non-
aqueous mercury, respectively), 8240 (volatile organics) and
8270 (semivolatile organics) of EPA document SW-846, Third
Edition.
Page 3 of9
sfc rmpr dewatered sludge d1ci.doc February 2010
Radioactive Material Profile Record: Sequoyah Fuels Corporation; dewatered raffinate sludge
D. CHEMICAL AND HAZARDOUS CHARACTERISTICS
1. DESCRIPTION AND HISTORY OF MATERIAL
c. The basis of hazardous material or waste determinations.
Attachment D lci
Table 3. Comprehensive List of Constituents
Phenols and Organic Acids
Benzoic acid 1 4,6-Dinitro-o-cresol
Benzyl alcohol 2,4-Dinitrophenol
2 -sec-Butyl-4,6-dinitrophenol l,q 2 -Methy l-4,6-dinitrophenol
4 -Chloro-3-methylphenol '1 2 -Nitrophenol
2-Chlorophenol 4 -Nitrophenol
Cresol (methyl phenols) Pentachlorophenol
2-Cyclohexyl-4,6-dinitrophenol 1,4 Phenol
2,4-Dichlorophenol Tetrachlorophenols
2,6-Dichlorophenol Trichlorophenols
2,4-Dimethylphenol
Phthalate Esters
Benzyl butyl phthalate ~i-n-butyl phthalate 1
Bis(2-ethylhexyl)phthalate ~imethyl phthalate
Diethyl phthalate Di-n-octyl phthalate
Nitroaromatics and Cyclic Ketones
Dinitrobenzene 1 Isophorone
2,4-Dinitrotoluene !'f_aphthoquinone
2,6-Dinitrotoluene Nitrobenzene
Page 4 of9
sfc rmpr dewatered sludge d1cLdoc
Page 1 of 6
1
February 2010
Radioactive Material Profile Record: Sequoyah Fuels Corporation; dewatered raffinate sludge
D. CHEMICAL AND HAZARDOUS CHARACTERISTICS
1. DESCRIPTION AND HISTORY OF MATERIAL
c. The basis of hazardous material or waste determinations.
Attachment D 1 ci
Table 3 • Comprehensive List of Constituents
Page 2 of 6
polyaromatic Hydrocarbons
Acenaphthene Dibenzo(a,h) anthracene
iAcenaphthylene 7H-Dibenzo(c,g)carbazole 1,4
:Anthracene Dibenzo(a,e)pyrene 1
Benzo (a) anthracene Dibenzo(a,h)pyrene 1,4
Benzo(a)pyrene Dibenzo(a,i)pyrene 1,. ~
Benzo(b)fluoranthene 1 Fluoranthene
Benzo(j)fluoranthene Fluorene
Benzo(k)fluoranthene Indeno(l,2,3-cd)pyrene
Benzo(g,h,i)perylene 3-Methylcholanthrene
Chrysene Naphthalene
Dibenz(a,h)acridine 1 Phenanthrene
Dibenz(a,j)acridine 1 Pyrene
Metals
!Aluminum Magnesium
Antimony Manganese
!Arsenic Mercury
Barium Molybdenum 3
Beryllium Nickel
Cadmium Potassium
Calcium 3 Selenium
Chromium Silver
Cobalt Sodium
Copper 'rhallium
Iron Vanadium
Lead Zinc
Page 5 of9
sfc rmpr dewatered sludge d1ci.doc February 2010
Radioactive Material Profile Record: Sequoyah Fuels Corporation; dewatered raffinate sludge
E. CHEMICAL AND HAZARDOUS CHARACTERISTICS
2. DESCRIPTION AND HISTORY OF MATERIAL
c. The basis of hazardous material or waste determinations.
Attachment Dlci
Table 3. Comprehensive List of Constituents
Page 3 of
Base/Neutrals
Acenaphthene 4-Chlorophenyl phenyl ether Heptachlor 2
Acenaphthylene Chrysene Heptachlor epoxide 2
Acetophenone 4,4' -DDD 2 Hexachlorobenzene
Aldrin 2 4,4' -DDE 2 Hexachlorobutadiene
~iline 4,4' -DDT 2 Hexachlorocyclopentadiene
IAnthracene Dibenz(a,j)acridine 1 Hexachloroethane
4-Aminobiphenyl Dibenz(a,h)anthracene Indeno(l,2,3-cd)pyrene
Aroclor-1016 Dibenzofuran Isophorone
~roclor-1221 Di-n-butyl phthalate Methoxychlor 2
~roclor-1232 l,3-Dichlorobenzene 3-Methylcholanthrene
~roclor-1242 l,4-Dichlorobenzene ~ethyl methanesulfonate
Aroclor-1248 l,2-Dichlorobenzene 2-Methylnaphthalene
Aroclor-1254 3,3'-Dichlorobenzidine lNaphthalene
Aroclor-1260 Dieldrin 2 l-Naphthylamine
Benzidine 1 Diethyl phthalate 2-Naphthylamine
Benzo(a) anthracene p-Dimethylaminoazobenzene 2-Nitroaniline
Benzo(b)fluoranthene 7,12-Dimethylbenz(a)anthracene 3-Nitroaniline
Benzo(k)fluoranthene a-,a-Dimethylphenethylamine 4-Nitroaniline
Benzo(g,h,i)perylene !Dimethyl phthalate Nitrobenzene
!Benzo(a)pyrene 2,4-Dinitrotoluene N-Nitroso-di-n-butylamine
Iex-BHC 2 2,6-Dinitrotoluene N-Nitrosodimethylamine
j3-BHC 2 Diphenylamine N-Nitrosodiphenylamine
a-BHC 2 l,2-Diphenylhydrazine N-Nitrosodipropylamine
y-BHC 2 Di-n-octyl phthalate N-Nitrosopiperidine
Bis(2-chloroethoxy)methane Endosulfan I 2 Pentachlorobenzene
Bis(2-chloroethyl)ether 1 Endosulfan II 2 Pentachloronitrobenzene
Bis (2-chloroisopropyl) ether Endosulfan sulfate 2 Phenacetin
Bis(2-ethylhexyl)phthalate Endrin 2 Phenanthrene
4-Bromophenyl phenyl ether Endrin aldehyde 2 2-Picoline
Butyl benzyl phthalate Endrin ketone 1 Pronamide
Chlordane 2 Ethyl methanesulfonate pyrene
6
4-Chloroaniline Fluoranthene l,2,4,5-Tetrachlorobenzene
1-Chloronaphthalene 1 Fluorene 1, 2, 4-Trichlorobenzene
2-Chloronaphthalene 2-Fluorobiphenyl 1,4 Toxaphene 2
Page 6 of9
sfc rmpr dewatered sludge d1ci.doc February 2010
Radioactive Material Profile Record: Sequoyah Fuels Corporation; dewatered raffinate sludge
F. CHEMICAL AND HAZARDOUS CHARACTERISTICS
3. DESCRIPTION AND HISTORY OF MATERIAL
c. The basis of hazardous material or waste determinations.
Attachment Dlci
Table 3. Comprehensive List of Constituents
Organocblor ine Pesticides and PCB's
Aldrin 2 Endr in aldehyde :/
ex-BHe 2 Heptachlor 2
I3-BHC 2 Heptachlor epoxide 1
o -BHC 2 ICepone z
y -BHC (Lindane) ~ Methoxychlor -;:
Chlordane 2 Toxaphene 2
4,4' -DDD 2 PCB-1016(Aroclor-1016)
4,4'-DDE ~ PCB-1221(Aroclor-1221)
4,4' -DDT 2 PCB-1232 (Aroclor-1232)
Dieldrin 2 ~CB-1242(Aroclor-1242)
Endosulfan I 2 PCB-1248 (Aroclor-1248)
Endosulfan II 2 PCB-1254 (Aroclor-1254)
Endosulfan sulfate 2 PCB-1260(Aroclor-1260)
Endrin -:2
Page 7 of9
sfc rmpr dewatered sludge d1cLdoc
Page 4 of 6
February 2010
Radioactive Material Profile Record: Sequoyah Fuels Corporation; dewatered raffinate sludge
F. CHEMICAL AND HAZARDOUS CHARACTERISTICS
3. DESCRIPTION AND HISTORY OF MATERIAL
c. The basis of hazardous material or waste determinations.
Attachment Dlci
Table 3. Comprehensive List of Constituents
Halogenated Volatiles
lBenzyl chloride 1 l,2-Dichlorobenzene
Bis(2-chloroethoxy)methane 1,3-Dichlorobenzene
Bis(2-chloroisopropyl)ether 1 1,4-Dichlorobenzene
IBromobenzene ). Dichlorodifluoromethane
Bromodichloromethane 1,1-Dichloroethane
Bromoform 1,2-Dichloroethane
Bromomethane 1,1-Dichloroethylene
Carbon tetrachloride trans-1,2-Dichloroethylene
Chloracetaldehyde J..4 Dichloromethane 1,4
Chloral 1,4 1,2-Dichloropropane
Chlorobenzene l,3-Dichloropropylene 1
Chloroethane 1, 1, 2, 2-Tetrachloroethane
Chloroform 1, 1, 1,2-Tetrachloroethane
1-Chlorohexane 1,4 Tetrachloroethylene
2-Chloroethyl vinyl ether 1 1, 1, 1-Trichloroethane
Chloromethane 1,l,2-Trichloroethane
Chloromethyl methyl ether 1 Trichloroethylene
Chlorotoluene 1 ~richlorofluoromethane
Dibromochloromethane Trichloropropane 1
Dibromomethane Vinyl chloride
Aromatic Volatiles
Benzene 1,4-Dichlorbenzene
Chlorbenzene Ethyl benzene
1,2-Dichlorobenzene Toluene
1,3-Dichlorobenzene Xylenes(Dimethyl benzenes)
Acentonitrile, Acrolein, Acrylonitrile
Acentonitrile crolein(Propenal) crylonitrile
Page 8 of9
sfc rmpr dewatered sludge d1ci.doc
Page 5 of 6
February 2010
Radioactive Material Profile Record: Sequoyah Fuels Corporation; dewatered raffinate sludge
F. CHEMICAL AND HAZARDOUS CHARACTERISTICS
3. DESCRIPTION AND HISTORY OF MATERIAL
c. The basis of hazardous material or waste determinations.
Attachment D 1 ci
Table 3. Comprehensive List of Constituents
Volatiles
A.cetone 1,1-Dichloroethene
!Acrolein trans-1,2-Dichloroethene
!Acryloni trile cis-1,3-Dichloropropene
~enzene trans-1,3-Dichloropropene
Bromochloromethane L 1,4-Difluorobenzene 1
Bromodichloromethane Ethanol 1
4-Bromofluorobenzene 1 ~thylbenzene
Bromoform iEthyl methacrylate
Bromomethane 2-Hexanone
2-Butanone (MEK) Iodomethane 1
Carbon disulfide Methylene chloride
Carbon tetrachloride 4-Methyl-2-pentanone
Chlorobenzene Styrene
Chlorodibromomethane 1,1,2,2-Tetrachloroethane
Chloroethane Toluene
2-Chloroethyl vinyl ether l,l,l-Trichloroethane
Chloroform 1,1,2-Trichloroethane
Chloromethane 1 Trichloroethene
Dibromomethane 1 Trichlorofluoromethane
1,4-Dichloro-2-butane 1,2,3-Trichloropropane
Dichlorodifluoromethane Vinyl acetate
1,1-Dichloroethane Vinyl chloride
1 ,2-Dichloroethane Xylene
Pag.e 6 of
1 Will not be provided because constituent is not listed in either
40 CFR 261, Appendix VIII or 40 CFR 264, Appendix IX.
2
4
Analytical results for organochlorine pesticides will
not be provided .
Will be provided and is in addition to the metals specified in the
RFI guidance document .
will not be provided because laboratory method does not normally
provide result.
Page 9 of9
6
sfc rmpr dewatered sludge d1ci.doc February 2010
RMPR Attachment 0.1 cjj
USPCI
_ A Subsidiary of
111111' Union Pacific Corporation
Analytical Services
'1322 Sourh 19r11 Wesr Avenue
Tulsa, OK 74107-6100
918/446-Ll62
918/415-0945 Fax
SEQUOYAH FUELS
P.O. BOX 610
GORE OK 74435
ATTENTION: SONNY EIDSON
RE: PROJECT: RFI
USPCI-AS REPORT: 9078
Under this cover USPCI Analytical Services is submitting the
analytical data for the following samples:
Lab Number
50000491
50000492
50000493
50000494
50000495
50000496
Customer Number
SD-13
SD-13D
SD-14
SD-15
SD-15DUP
SD-16
These samples were analyzed using EPA or other recognized methodology
as specified in the report. Each test is performed under a rigorous
QA/QC program including blanks. method controls and matrix spikes.
All methods are calibrated using authentic reference materials with
a minimum of a three point calibration curve as appropriate.
All practical quantitation limits are validated and reflect method
specific or project specific requirements. Some detection limits may
be listed as higher than the targeted program limits due to sample
specific interferences or limited sample size.
If you need help in evaluating the data or need further information
please call the laboratory at 918-446-1162.
Respectfully submitted for
USpe! .;;;;;)::0
~eth R. Walker
Quality Assurance Officer
Our Mission:
Provide the highest quality laboratory management services that consistently meet or exceed customer
needs and regulatory requirements at competHive costs white enhancing shareholder value.
_ A Subsidiary of
'111111 Union Pacific Corporation
Analytical Services
4322 South 49th West Avenue
T ulsa, OK 74107-6100
918/446-1 162
918/445-0945 Fax
SAMPLE IDENTIFICATION: 50000493
CUSTOMER IDENTIFICATION: SD-14
PROJECT NUMBER: RFI
REPORT NUMBER: 9078
DATE SAMPLED: 01/25/95
TYPE OF MATERIAL: SLUDGE
16 Feb 9S PAGE
SONNY EIDSON
SEQUOYAH FUELS
P.O. BOX 610
GORE OK 74435
DATE SUBMITTED: 01/26/95
DATE COMPLETED: 02/16/95
REFERENCE PRACTICAL
13
!..!PA~RA~M.E!!oUT£!Ec!l.R ___________ ""ME ... T ..... H...,O~D'--_ QUANTI TAT ION LIMIT wRE",-,S~U:.!oL~T _____ _
Mercury (Total)
Volatiles
Acetone
Acetonitrile
Acrolein
Acrylonitrile
Benzene
Bromodichloromethane
Bromoform
2-Butanone
Carbon disulfide
Carbon Tetrachloride
Chlorobenzene
Chloroethane
2-Chloroethyl vinyl ether
Chloroform
Chlorodibromomethane
1,4-Dichloro-2-butene
Dichlorodi£luoromethane
1,1-Dichloroethane
1,2-Dichloroethane
1,1-Dichloroethene
trans-l,2-Dichloroethene
1,2-Dichloropropane
cis-l,3-Dichloropropene
SW 7471
SW 8240
SW 8240
SW 8240
SW 8240
SW 8240
SW 8240
SW 8240
SW 8240
SW 8240
SW 8240
SW 8240
SW 8240
S\oJ 8240
SW 8240
SW 8240
SW 8240
SW 8240
SW 8240
SW 8240
SW 8240
SW 8240
SW 8240
SW 8240
0.01 mg/kg
0.1 mg/kg
0.1 mg/kg
0.1 mg/kg
0.1 mg/kg
0.005 mg/kg
0 .005 mg/kg
0.005 mg/kg
0.1 mg/kg
0.005 mg/kg
0.005 mg/kg
0.005 mg/kg
0.005 mg/kg
0.01 mg/kg
0.005 mg/kg
0.005 mg/kg
0.1 mg/kg
0.005 mg/kg
0.005 mg/kg
0.005 mg/kg
0.005 mg/kg
0.005 mg/kg
0.005 mg/kg
0.005 mg/kg
BDL = BELOW QUANTITATION LIMIT % REC = PERCENT RECOVERY
J = VALUE REPORTED BELOW QUANTITATION LIMIT
Our Mission:
0.34 mg/kg
BDL mg/kg
BDL mg/kg
BDL mg/kg
BDL mg/kg
BDL mg/kg
BDL mg/kg
BDl. mg/kg
0.3 mg/kg
BDL mg/kg
BDL mg/kg
BDL mg/kg
BDL mg/kg
BDL mg/kg
BDL mg/kg
BDL 109/kg
BDL mg/kg
BDL mg/kg
BDL mg/kg
BDL mg/kg
BDL 109/kg
BDL mg/kg
BDL mg/kg
BDL mg/kg
(T) = TOTALS
Provide the highest quality laboratory managemenl services that consistently meet or exceed customer
needs and regulatory requirements at competitive costs while enhancing shareholder value.
Analytical Services
4.)22 South 49th West Avenue
Tulsa, OK 74l07-6100
918/446-1162
918/145-0945.Fax
SAMPLE IDENTIFICATION: 50000493
CUSTOMER IDENTIFICATION: 8D-14
PROJECT NUMBER: RFI
REPORT NUMBER: 9078
DATE SAMPLED: 01/25/95
TYPE OF MATERIAL: SLUDGE
PARAMETER
trans-1,3-Dichloropropene
Ethyl methacrylate
2-Hexanone
4-Methyl-2-pentanone
Methylene chloride
Styrene
1, 1, 1,2-Tetrach1oroethane
1,1,2,2-Tetrachloroethane
Tetrachloroethene
Toluene
1,1, I-Trichloroethane
1,1,2-Trichloroethane
Trichloroethene
Trichlorofluoromethane
1,2,3-Trichloropropane
Vinyl acetate
Vinyl chloride
Total xylenes
Semivolatiles
Acenaphthene
Acenaphthylene
Acetophenone
Aldrin
4-Aminobiphenyl
Aniline
Anthracene
REFERENCE
METHOD
SW 8240
SW 8240
SW 8240
SW 8240
SW 8240
SW 8240
SW 8240
SW 8240
SW 8240
SW 8240
SW 8240
SlY 8240
SW 8240
SW 8240
SW 8240
SW 8240
SW 8240
SlY 8240
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
16 Feb 95 PAGE 14
SONNY EIDSON
SEQUOYAH FUELS
P.O. BOX 610
GORE OK 74435
DATE SUBMITTED: 01/26/95
DATE COMPLETED: 02/16/95
PRACTICAL
QUANTITATION LIMIT RESULT
0.005 mg/kg BDL mg/kg
0.005 mg/kg BDL mg/kg
0.05 mg/kg 0.08 mg/kg
0.05 mg/kg BDL mg/kg
0.01 mg/kg BDL mg/kg
0.005 mg/kg BDL mg/kg
0.005 mg/kg BDL mg/kg
0.005 mg/kg BDL mg/kg
0.005 mg/kg BDL mg/kg
0.005 mg/kg BDL mg/kg
0.005 mg/kg BDL mg/kg
0.005 mg/kg BDL mg/kg
0.005 mg/kg BDL mg/kg
0.005 mg/kg BDL mg/kg
0.005 mg/kg BDL mg/kg
0.05 mg/kg BDL mg/kg
0.01 mg/kg BDL mg/kg
0.005 mg/kg BDL mg/kg
0.05 mg/kg BDL mg/kg
0.05 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.05 mg/kg BDL mg/kg
BDL = BELOW QUANTITATION LIMIT % REC = PERCENT RECOVERY
J = VALUE REPORTED BELOW QUANTITATION LIMIT
(T) = TOTALS
Our Mission:
Provide the highest quality laboratory management services thai consistently meet or exceed customer
needs and regulatory requirements at competitive costs while enhancing shareholder value.
USPCI
_ A Subsidia of
'lilli' Union pac~c Corporation
Analytical Services
I\E2 South 49th West Avenue
Tulsa, OK 71107-6lO0
918/446-l162
918/415-094 5 Fax
SAMPLE IDENTIFICATION: 50000493
CUSTOMER IDENTIFICATION: SD-14
PROJECT NUMBER: RFI
REPORT NUMBER: 9078
DATE SAMPLED: 01/25/95
TYPE OF MATERIAL: SLUDGE
REFERENCE
16 Feb 95 PAGE
SONNY EIDSON
SEQUOYAH FUELS
P.O. BOX 610
GORE OK 74435
DATE SUBMITTED:
DATE COMPLETED :
PRACTICAL
01/26/95
02/16/95
IS
PARAI'IETER METHOD OUANTITATION LIMIT RESULT
Arocior-1016
Aroc1or-12~1
Aroc1or-1232
Aroc1or-1242
Aroclor-1248
Aroclor-1254
Aloc1or-1260
Benzo(a)anthracene
Benzo(b)fluoranthene
Benzo(k)fluoranthene
Benzo(g,h,i)perylene
Benzo(a)pyrene
Benzyl alcohol
a1pha-BHC
beta-BHC
delta-BHC
gamma-BHC (Lindane)
Bis(2-chloroethoxy)methane
Bis(2-chloroethy1)ether
Bis(2-chloroisopropyl)ether
Bis(2-ethylhexy1)phthalate
4-Bromophenyl phenyl ether
Butyl benzyl phthalate
Chlordane
4-Chloroaniline
2-Ch1oronaphtha1ene
2-Ch1orophenol
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
2 mg/kg BDL mg/kg
2 mg/kg BDL mg/kg
2 mg/kg BDL mg/kg
2 mg/kg BDL mg/kg
2 mg/kg DDL mg/kg
2 mg/kg DDL mg/kg
2 mg/kg DDL mg/kg
0.05 mg/kg BDL mg/kg
0.05 mg/kg BDL mg/kg
0.05 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.05 mg/kg BDL mg/kg
0.4 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg DDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg DDL mg/kg
1 mg/kg DDL mg/kg
0.4 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
BDL = BELOW QUANTITATION LIMIT % REC = PERCENT RECOVERY (T) = TOTALS
J = VALUE REPORTED BELOW QUANTITATION LIMIT
Our Mission:
Provide the highest quality laboratory management services that consistently meet or exceed customer
needs and regulatory requirements at competitive costs while enhancing shareholder value.
USPCI _ A Subsidiary of '11m' Union Pacific Corporation
Analytical Services
4322 South 1\9th West Avenue
Tulsa, OK 74107·6100
918/446-1162
918/445·0945 Fax
SAMPLE IDENTIFICATION: 50000~
CUSTOMER IDENTIFICATION: SD-14
PROJECT NUMBER: RFI
REPORT NUMBER: 9078
DATE SAMPLED: 01/25/95
TYPE OF MATERIAL: SLUDGE
REFERENCE
16 Feb 95 PAGE
SONNY EIDSON
SEQUOYAH FUELS
P.O. BOX 610
GORE OK 74435
DATE SUBMITTED :
DATE COMPLETED:
PRACTICAL
01/26/95
02/16/95
16
PARAMETER METHOD QUANTITATION LIMIT RESULT
4-Chlorophenyl phenyl ether
Chrysene
2-Methylphenol
3-and 4-methylphenol
4,4'-DDD
4,4'-DDE
4,4'-DDT
Dibenz(a,h)anthracene
Dibenzofuran
Dibenz(a,e)pyrene
Di-n-butylphthalate
1,2-Dichlorobenzene
1,3-Dichlorobenzene
1,4-Dichlorobenzene
3,3'-Dichlorobenzidine
2,4-Dichlorophenol
2,6-Dichlorophenol
Dieldrin
Diethyl phthalate
p-Dimethylaminoazobenzene
7, 12-Dimethylbenz(a)anthracene
1,1-Dimethylphenethy1amine
2,4-Dimethy1phenol
Dimethylphthalate
4,6-Dinitro-2-methylphenol
2,4-Dinitrophenol
2,4-Dinitrotoluene
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
0.2 mg/kg BDL mg/kg
0.05 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.4 mg/kg DDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
1 mg/kg BDL mg/kg
1 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
BDL = BELOW QUANTITATION LIMIT % REC = PERCENT RECOVERY (T) = TOTALS
J = VALUE REPORTED BELOW QUANTITATION LIMIT
Our Mission:
Pro~ide the highest quality laboratory management services that consistently meet or exceed customer
needs and regulatory requirements at competitj~e costs while enhancing shareholder value_
Analytical Services
4322 South 49th West Avenue
Tulsa, OK 7-1107-6100
918/446-1162
9l8/445-0945 Fax
SAMPLE IDENTIFICATION: 50000493
CUSTOMER IDENTIFICATION: SD-14
PROJECT NUMBER: RFI
REPORT NUMBER: 9078
DATE SAMPLED: 01/25/95
TYPE OF MATERIAL: SLUDGE
PARAMETER
2,6-Dinitrotoluene
Di-n-octylphthalate
1,2-Diphenylhydrazine
Diphenylamine
Endosulfan I
Endosulfan II
Endosulfan sulfate
Endril1
Endrin aldehyde
Ethyl methanesulfonate
Fluoranthene
Fluorene
Heptachlor
Heptachlor epoxide
Hexachlorobenzene
Hexachlorobutadiene
Hexachlorocyclopentadiene
Hexachloroethane
Indeno(1,2,3-cd)pyrene
Isophorone
Methoxychlor
3-Methylchloanthrene
Methyl methanesulfonate
2-Methylnaphthalene
Naphthalene
1,4-Naphthoquinone
1-Naphthylamine
REFERENCE
METHOD
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
16 Feb 95 PAGE 17
SONNY EIDSON
SEQUOYAH FUELS
P.O. BOX 610
GORE OK 74435
DATE SUBMITTED: 01/26/95
DATE COMPLETED: 02/16/95
PRACTICAL
QUANTITATION LIMIT RESULT
0.2 mg/kg EDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 rng/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.05 mg/kg BDL mg/kg
0.05 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.05 mg/kg BDL mg/kg
0.05 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
BDL = BELOW QUANTITATION LIMIT % REC = PERCENT RECOVERY (T) = TOTALS
J = VALUE REPORTED BELOW QUANTITATION LIMIT
Our Mission:
Provide the highest quality laboratory management services that consistently meet or exceed customer
needs and regulatory requirements at competitive costs while enhancing shareholder value.
~---~PCI
_ A Subsidiary of
'111111 Union Pacific Corporation
Analytical Services
4322 50mh 49rh West Avenue
Tulsa, OK 7,1107-6100
918/446-1162
9l8/445-0915 Fax
SAMPLE IDENTIFICATION: 50000493
CUSTOMER IDENTIFICATION: SD-14
PROJECT NUMBER: RFl
REPORT NUMBER: 9078
DATE SAMPLED: 01/25/95
TYPE OF MATERIAL: SLUDGE
REFERENCE
16 Feb 95 PAGE
SONNY EIDSON
SEQUOYAH FUELS
P.O. BOX 610
GORE OK 74435
DATE SUBMITTED:
DATE COMPLETED:
PRACTICAL
01/26/95
02/16/95
18
EARAMEIER METHOD OUANTITATION LIMIT RESULT
2-Naphthylamine
2-Nitroaniline
3-Nitroaniline
4-Nitroaniline
Nitrobenzene
2-Nitrophenol
4-Nitrophenol
N-Nitrosodi-n-butylamine
N-Nitrosodimethylamine
N-Nitrosodiphenylamine
N-Nitrosodipropylamine
N-Nitrosopiperidine
Pentachlorobenzene
Pentachloronitrobenzene
Pentachlorophenol
Phenacetin
Phenanthrene
Phenol
2-Pico1ine
Pronamide
Pyrene
1,2,4,5-Tetrachlorobenzene
2,3,4,6-Tetrachlorophenol
Toxaphene
1,2,4-Trich1orobenzene
2,4,5-Trichloropheno1
2,4,6-Trichlorophenol
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
0.2 mg/kg BDL mg/kg
1 mg/kg BDL mg/kg
1 mg/kg BDL mg/kg
0.4 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
1 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
1 mg/kg BDL mg/kg
0.4 mg/kg BDL mg/kg
0.05 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.05 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
0.2 mg/kg BDL mg/kg
BDL = BELOW QUANTITATION LIMIT % REC = PERCENT RECOVERY (T) == TOTALS
J == VALUE REPORTED BELOW QUANTITATION LIMIT
Our Mission:
Provide the highest quality l1\.boratory management services that consistently meet or exceed customer
needs and regulatory requirements at competitive costs while enhancing shareholder value.
16 Feb 95 PAGE 3
Analytical Services
·4322 South 49th West Avenue
Tulsa, OK 74107-6100
918/446-1 !62
918/445-0945 Fax
SAMPLE IDENTIFICATION:
CUSTOMER IDENTIFICATION:
PROJECT NUMBER: RFl
REPORT NUMBER: 9078
DATE SAMPLED: 01/25/95
TYPE OF MATERIAL: SLUDGE
50000493
SD-14
SONNY EIDSON
SEQUOYAH FUELS
P.O. BOX 610
GORE OK 74435
DATE SUBMITTED: 01/26/95
DATE COMPLETED: 02/16/95
REFERENCE RECOVERY
....,I'A....,R .... A~M~E~TE~R~ _____ -:--____ M ..... E .... T ...... H""'OD"'--_ =LI"",M"-'!I,-",T"",S-,,-,C %.w)'----___ RESULT C%)
Volatiles-Surrogates
1,2-Dichloroethane-d4
Toluene-dB
Bromofluorobenzene
Semivolatiles-Surrogates
2-Fluorophenol
dS-Phenol
dS-Nitrobenzene
2-Fluorobiphenyl
2,4,6-Tribromophenol
d14-Terphenyl
SW 8240
SW 8240
SW 8240
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
SW 8270
76 -114
88 -110
86 -115
21 -100
10 -94
35 -114
43 -116
10 -123
33 -141
D indicates sample was diluted to a concentration in which surrogates
cannot be accurately measured. The value listed reflects the dilution
factor. Some compounds may be run less dilute for better detection.
81
89
80
72
88
83
83
89
64
I indicates interference of surrogate compound, recoveries indeterminable.
Surrogate recoveries flagged as either high CH) or low (L) indicates
sample results may be biased either high or low respectively, and the
sample results should be considered as estimates.
OUf Mission:
Provide the highest quality laboratory management services that consistently meet or exceed customer
needs and regulatory require~nts at compe«live costs while enhancing shareholder value.
L
USPCI
- A Subsidia of '11111' Union Pac*c Corporation
Analytical Services
4322 SOllth 49th West Avenue
Tulsa, OK 7·1107 -6100
918/446-1162
918/445-0945 Fax
SONNY EIDSON
SEQUOYAH FUELS
P.O. BOX 610
GORE OK 74435
QA/QC Report
Cross Reference
Project Name: RFI
USPCI SAMPLE
50000491
50000492
50000493
50000494
50000495
50000496
Our Mission:
ID CUSTOMER ID
SD-13
SO-13 OUP
SO-14
SO-lS
SO-15 OUP
SD-16
Provide the highest quality laboratory management services that consistently meet or exceed customer
needs and regulatory requirements at competitive costs while enhancing shareholder value.
QA/QC Report
Holding Times
Date at Lab: 1445 01/26/95
Holding Times
PARAMETER SAMPLE ID HOLDING TIME
Volatiles 50000491 14 days
50000492
50000493
50000494
50000495
50000496
Semi-50000491 14 days for
Volatiles 50000492 extraction,
50000493 40 days after
50000494 for analysis
50000495
50000496
T. Mercury 50000491 13 days
50000492
50000493
50000494
50000495
50000496
SAMPLING DATE
1500 01/24/95
1500 01./24/95
0945 01./25/95
1500 01./25/95
1500 01/25/95
1130 01/25/95
1500 01/24/95
1500 01/24/95
0945 01/25/95
1500 01/25/95
1500 01/25/95
1130 01/25/95
1500 01/24/95
1500 01/24/95
0945 01/25/95
1500 01/25/95
1500 01/25/95
1130 01/25/95
EXTRACTION ANALYSIS
01/30/95
01/30/95
01/30/95
02/03/95
01/30/95
01/30/95
02/01/95 02/10/95
(All samples)
02/2-3/95
(All samples)
Samples exceeding method recommended holding times are indicated with an asterisk (*).
QA/QC REPORT
METALS • SOIL
MATRIX SPIKE: 50000496 ac FILE 10: 50000497
PARAMETER
MERCURY
BLAIIIC SNI'LE
RESULTS MG/L RESULTS Me/L
BOL 0.00048 HG
MG/L UNIT VALUES ARE BASED ON OIGESTATE CONCENTRATION
sPIKE LEVEL SPIKE I SPIKE I (
RESULTS MG/L RESULTS Me/L RESULTS Me/L
0.0100 0.0109 0.0100
* = OUT OF QC LIMIT BDL = BELOU DETECTION LIMIT
RECOVERY RECOVERY AVERAGE
T II RECOVERY DIFFERENCE
104.3% 95 .4% 99.9% 8.5%
METHOO M.CTRL
CONTROL RECOVERY
0.0098 98.0%
+ = INSTRUMENT SPIKE (QC ACCEPTABLE LIMIT IS 75-125%)
QA/QC REPORT
VOLATILES BY GC/MS -SOIL
METHOO CONTROL
QC FILE 10: 50000497
BLANK SAMPLE SPIKE lEVEL SPlICE I SPIKE II RECOVER,/, RECOVERY QC LIMITS
PAINIETER RESULTS UG/KG RESUlTS UG/KG UG/KG RESULTS UG/ICG RESULTS UGlKG I II RPD RPD X REt
1,1-0iehloroethene BOL BOL 40 48 47 120~ 118% 2 35 0-Z34
Methylene chloride BOL BOL 40 45 45 106% 105% 1 29 O-Z21
trans-1,Z-Oichloroethene BOL BOL 40 45 45 113% 112% 1 15 54-156
1,1-0fchloroethane BOL BOL 40 44 43 109" 108% 1 13 59-155
Chloroform BOL BOL 40 45 4S 114% 113% 0 15 51-138
1,t,t-Trichloroethane BOL BOL 40 45 45 112% 112% a 17 52-162
Carbon tetrachloride BOl BOL 40 49 48 123% 119% 3 8 70-140
Benzene BDL BoL 40 43 42 109% 106% 2 19 37-151
l,Z-Oichloroethane BoL BOL 40 48 47 119% 118% t 18 49-155
Trichloroethene BDL BDL 40 45 45 114% 112% 2 11 71-157
1,2-0iehloropropane BOL BOL 40 45 43 111% 108% 3 38 0-210
9romodiehloromethane BOL BOL 40 46 45 114% 112% 1 18 35-155
cis-1,3-0fchloropropene BOL BOL 40 45 44 113% 110% 3 47 0-227
TolUene BOL BOL 40 44 43 110% 107"A. 3 17 47-150
trans-l,3-0ichloropropene BOL BOL 40 39 38 97% 94% 3 16 17-183
1,1,Z-Trichloroethane BOL BOL 40 49 50 122% 123% 1 16 52-150
Tetrachloroethene BOL BOL 40 41 39 102% 96% 5 13 64-148
Chlorodibromomethane BOL BOL 40 48 47 119% 116% 2 16 53-149
Chlorobenzene BOL BOL 40 45 43 11'" 107% 3 20 37-160
Ethylbenzene BOL BDL 40 47 44 116% 110"" 5 21 37-162
9romoforlll BOL BOL 40 49 46 121% 114% 5 19 45-169
1,t,Z,Z-Tetrachloroethane BDL BOL 40 55 53 136% 130% 5 17 46-157
BOL = BELOW DETECTION LIMITS NIS = HOT IN SPIKE MIX # = OUT OF QC LIMITS D = DETECTABLE
!lA/QC REPORT
VOLATILES BY GC/MS -SOIL MATRIX SPlICE: 50000382
QC FILE ID: 50000497
BLANK SAMPLE SPlICE LEVEL SPIKE I SPIKE II RECOVERY RECOVERY QC LIMITS
PARAMETER RESULTS UG/lG RESULTS UGJKG UG/KG RESULTS UG/ICG RESULTS UG/KG I 1/ RPD RPD % REC
1,1-0ichloroethene BOL BOL 40 49 51 124% 12ft. 3 35 0-234
Methylene chloride BOL BOL 40 53 56 102% 110X 7 29 0-221
trans-l,2-Dichloroethene BOL BOL 40 41 39 101% 97"-' 5 15 54-156
l,l-Dichloroethane BOL BOL 40 44 43 110% 108% 2 13 59-155
Chloroform BOL SOL 40 49 48 123% 120% 2 15 5,.,38
1,1,1-Trichloroethane BOL SOL 40 50 49 125% 122% 2 17 52-162
Carbon tetrachloride BOL SOL 40 59 60 148% II 150% #I 1 8 70-140
Benzene BDL BOL 40 43 42 lOr/. 106% 1 19 37-151
1,Z-Dlchloroethene BOL SOL 40 55 55 138% 138% 1 18 49-155
Trichloroethene BOL BOL 40 77 76 192% II 190% It 1 11 71-157
1,Z-Oichloropropane BOL BDL 40 44 43 111% 106% 4 38 0-210
Sromcdichloromethane BOL BOL 40 5' 48 127% 120% 6 18 35-'55
cll-l,3-0ichloropropene BOL BOL 40 43 41 108% 102% 6 47 0-227
Toluene BOL BDl 40 42 41 104% 101% 3 17 47-150
trans-l,l-Dichloropropene BOL BOL 40 37 35 93% 88% 5 16 17-183
',l,Z-Trichloroethane SOL BOl .40 45 38 113% 96% 16# 16 5Z-150
Tetrachloroethene BOl BDL 40 44 45 110% 111% 1 13 64-148
Chlorodfbromomethane BOL BOL 40 54 54 136% 135% 1 16 53-149
Chlorobenzene BOL BOL 40 42 41 106% 10Z% 3 20 37-160
Ethylbenzene BOl BOL 40 46 45 116% 113% 3 21 37-162
BrOllOfonn BDL BDL 40 56 54 140% 135% 3 19 45-169
l,1,2,Z-Tetrachloroethane BOL BOL 40 4 1 10% # 1% II 157# 17 46-157
BOL = BELOW DETECTION LIMITS HIS = NOT IN SPIKE MIX # = OUT OF QC LIMITS o :: DETECTABLE
QA/QC REPORT
SEMIVOLATILE SOIL
METHOD CONTROL
QC FILE 10: 50000497
BLANK SAMPLE SPIKE LEVEL SPIKE I SPlICE II RECOVERY RECOVERY AVERAGE
PARAMETER RESULTS MG/KG RESULTS MG/KG RESULTS MG/KG RESULTS MG/KG RESULTS Ma/KG [ II RECOVERY DIFFEREIiCE
4-NITROPHENOL # BOL BOL 1.60 1.52 1.45 94.BX 90.8% 92.8% 4.3)';
2,6-DINITROTOLUENE SOL BOL 0.80 0.80 0.87 100.1% 108.8% 104.5% 8.3)';
2,4'0INITROTOLUENE # BOL BOL 0.80 0.81 0.83 101.3% 103.8% 102.6% 2.4%
DIETHYL PHTHAlATE SOL BOL 0.80 0.86 0.80 107.1% 100.0% 103.6% 6.9%
4-CHLOROPHENYl PHENYL ETHER BOL BOl 0.80 0.80 0.94 100.5% 117.'% 108.8% 15.3%
FLUORENE SOL BOL 0.80 0.91 0.96 114.1% 120.0% 117.0% 5.1%
4,6-0INITRO-2-METHYLPHENOL BOL BOL 1.60 1.n 1.64 107.4% 102.7% 105.0r. 4.5%
N-NITROSO-OI-PHENYLAMINE BDL BOL 0.80 0.43 0.45 54.0% 56.0r. 55.0% 3.6)';
4-BROMOPHENVL PHENYL ETHER SOL BOl 0.80 0.91 0.90 114.0% 112.3% 113.2% 1. 5%
HEXACHLOROBENZENE BOL BOL 0.80 0.95 0.92 118.9% 114.7% 116.8% 3.6%
PENTACHLOROPHENOL , BOl BOl 1.60 1.61 1.53 100.8% 95.3% 98.1% 5.6%
PHENANTHRENE BOL BOl 0.80 0.85 0.83 106.8% 104.3% 105.6% 2.4%
ANTHRACENE BOl BOl 0.80 0.89 0.89 111.7'1. 111.7% 111.7% 0.0%
OI-N-BUTYl PHTHALATE SOL BOl 0.80 0.86 0.82 107.3% 102.5% 104.9% 4.6%
PYRENE #. BOL BOL 0.80 0.90 0.79 112.0% 98.2% 105.1% 13.1%
BENZO(A)ANTHRACENE SOL BOL 0.80 0.81 0.74 101.3% 92.2% 96.7"1. 9.4%
CHRYSENE BOl BOL 0.80 0.90 0.82 112.7% 103.1% 107.9% 8.9%
BIS(2-ETHYLHEXYl} PHTHALATE BOl BOL 0.80 0.96 0.89 119.8% 111.5% '15.6% 7.2%
DI-N-OCTYl PHTHALATE BOl BOl 0.80 1.01 1.14 126.6% 142.3% 134 .5% 11.7% BENZO(B)FLUORANTHENE BOl SOL 0.80 0.89 0.92 111.8% 115.0% 113.4% 2.8%
BEN20(K) FlUORANTHENE SOL BOL 0.80 1.18 1.22 147.3% 152.8% 150.1% 3.7% BENZO(A}PYRENE BOL BOl 0.80 0.97 0.99 121.8% 123.8% 122.8% 1.6% INOENO(1,2,3-cd)?YRENE BOL BOL 0.80 1.07 1.00 133.2% 124.7% 129.0% 6.6% DIBENZO(A,H)ANTHRACENE BDL BOl 0.80 1.00 0.96 124.9% 120.4% 122.6% 3.6%
BENZO(G,H,J)PERYLENE BDL BDl 0.80 1.10 1.05 137.4% 131.2% 134.3% 4.6%
# = SW 846 SPIKE CMPD. BOL = BeLow Detection Limits NIS = Not in Spike Mix • = Out of QC limits D = Detectable
GA/QC REPORT
SEMIVOLATllE SOIL
MATRIX SPlICE: 50000491
QC FILE 10: 50000497
BLAIIK SAlFLE SPIKE lEVEl SPIKE I SPIKE II RECOVERY RECOVERY AVERAGE
PARMETER RESULTS NG/lG RESUlTS MIi/l:G RESUlTS MG/G RESUlTS MIi/KG RESULTS IIG/KG I II RECOVERY OIFFEREIiCE
PHENOL , BOl BOt. 1.60 0.89 0.92 S5.9~ 57.6% 56.7X 3.0X
81S(2-CMLORO-ETHYL)ETHER BOl BOL 0.80 0.75 0.75 94.~ 94.3% 94.3% O.~
2-CHLOROPHENOL # BOl BOt. 1.60 0.62 0.71 38.9X 44.2% 41.5% 12.7".4
1.3-01CHLOROBENZENE BOt. BOt. 0.80 0.92 0.85 115.1% 106.9% 111.0% 7.4%
1,4-DICHLOROBENZENE , BOt. BDL 0.80 0.91 0.98 114.'" '22.6% , 18.4% 7.2%
BIS(Z-CHlORO-ISOPROPYl)ETHER BOt. BOt. 0.80 0.88 0.87 109.5% 109.2% 109.4% 0.2%
N-NITROSO-DI-N-PROPYlAMINE # BDl BOL 0.80 0.00 0.00 0.0% * 0.0% * 0.0% ... 0.0%
HEXACHLOROETHANE BOl BOt. 0.80 0.78 0.76 97.4% 95.2% 96.3% 2_3%
NITROBENZENE BOl BOl 0.80 0.93 0.87 "6. '" 108.8% 112.5% 6.5%
ISOPHORONE BOl BOl 0.80 1.02 1.00 127.9% 124.7% 126.3% 2.6%
2 -II ITROPHEIiOt. BOl BOL 1.60 0.32 0.36 19.9% ... 22.7% ... 21.3% * 13.3%
2,4-DIMETHYlPHENOl BOl BOl 1.60 1.36 1.31 84.9% 81.8% 83.4% 3.7%
BIS(2-CHlOROETHOXY)HETHANE BOL BOL 0.80 0.84 0.82 104.5% 102.9% 103.7% 1.5%
2,4-DICHlOROPHENOl BOl BDL 1_60 0.63 0.69 39.6% 43.0" 41.3% 8. ,%
1,2,4-TRICHlOROBEN2ENE # BOL BOt. 0.80 0.94 0.98 117.7".4 123 .0% 120_3% 4.5%
NAPHTHALENE BOL BOL 0.80 0.84 0.85 105.6% 106.4% 106.0% 0_8~
HEXACHt.OROBUTAOIEIIE BOL BOL 0.80 0.84 0.80 104.7".4 99.7".4 102.2"" 4.8%
4-CHlORO-3-METHYlPHENOL , BOL BOl 1_60 1.40 1.40 87.5% 87.3% 87.4% 0.2%
HEXACHLOROCYCt.OPENYADIENE BOL SOL 0.80 0.28 0.26 35.5% 32.1X 33.8% 10.0%
2,4,6-YRJCHlOROPHENOL BDl BOL 1.60 0_25 0.31 15.8% • 19.3% • 17.6% ... 19.8%
2-CHt.ORONAPHTHALENE BOL BOL 0.80 0.89 0.87 111. 1% 108.8% 109.9% 2.1%
DIMETHYL PHTHALATE 80l BOL 0.80 0.86 0.85 107.7% 106.3% 107.0% 1.2%
ACEIlAPHTHYLENE BOL BOL 0.80 0.93 0.94 115.7X 117.3% 116.5% 1.3% ACENAPHTHENE tJ BOL BOL 0.80 0.85 0.85 106.3% 106.3% 106.3~ 0.0%
2,4-DINITROPHENOL BOL SOL 1.60 0.03 0.00 1.7% 0.0% * 0.8% 200.0%*
# = sw 846 SPIKE CMPO. BOL = 8elow Detection Limits HIS Not in Spike Mix * = OUt of QC Limits 0 = Detectable
QA/QC REPORT
SEMIVOLATIlE SOIL
MATRIX SJ»IKE: 50000491
QC FilE 10: 50000497
BlAIIK SAMPLE SPIKE lEVEL SPIKE I SPIKE II REOOVERY RECOVERY AVERAGE
PARAIIETEI RESULTS lli/KG RESUlTS MG/KG RESULTS JlG/ICG RESUlTS MG/ICG RESULTS MG/ICG J II RECOVERY DIffERENCE
4-IIITROPNENOL tI BDL BDL 1.60 0.03 0.03 2.0% 1.9% 2.0% 6.3%
2,6-DINITROTOlUENE BOl BOL 0.80 0.80 0.80 100.0% 100.4% 100.2% 0.4~
2.4-DINITROTOlUENE # BOL BOL 0.80 0.79 0.78 99.1% 97.7% 98.4% 1.4~
DIETHYl PHTHALATE SOL BOl 0.80 0.97 0.96 120.9% " 119.6% * 120.2% " 1.1%
4-CHlOROPHENYL PHENYL ETHER BOL BOl 0.80 0.91 0.92 113.7% 114.5% 114.1% 0.7"-'
FLUORENE BOL BOL 0.80 0.96 0.97 119.4Y. 121.5% * 120.4% 1.7%
4.6-0 III ITRO-2-METHYlPHENOl BOL BOL , .60 0.14 0.15 8.9% 9.6% 9.3% 7.0%
N-NJTROSO-DI-PHENYLAMINE BDl BOL 0.80 0.39 0.42 49.1% 52.4% 50.8% 6.6%
4-BROMOPHENYL PHENYL ETHER BOL BOL 0.80 0.92 0.95 114.5% 118.5% 116.5% 3.5%
HEXACHlOROBENZENE BOL BOL 0.80 0.95 0.96 118.8% 119.6% 119.2% 0.71.
PENTACHLOROPHENOl # BOL BOL 1.60 0.16 0.16 10.0% * 10.2% " 10.1% * 2.7%
PHENANTHRENE BDL BOl 0.80 0.96 0.86 119.4% 107.3% 113.4% 10.7%
ANTHRACENE BDL SOL 0.80 0.90 0.92 112.1% 115.0% 113.6% 2.6"
OI-N-BUTYl PHTHALATE BOL BOL 0.80 0.86 0.93 107.3% 116.2% "1.8" 7.9%
PYRENE II BOL SOL 0.80 0.90 0.90 112 .7% 112.7% 112.7% 0.0%
BENZO(A)ANTHRACENE BOL BOL 0.80 0.82 0.64 103.'% 105.0% 104.'% , .8%
CHRYSENE BOl BDL 0.80 0.95 0.90 "8.2% 112.7"-' 115.4% 4.7%
BIS(Z-ETHYLHEXYL) PHTHALATE BOL BOL 0.80 1.04 1.05 130.6% '30.7% 130.6" O. I"
DI-N-OCTYl PHTHALATE BOL BOL 0.80 1.12 0.93 139.9% 116.2% 128.0% 18.5%
BENZO(B)FLUORANTHENE BOL BDL 0.80 0.91 0.93 113.9% 116.1% 115.0X 1.9"
BENZO(K)fLUOlANTHENE BOL BOL 0.80 1.17 1.23 145.9" 154.1% 150.0X 5.5X
BENZO(A)PYIIEHE BOL BOL 0.80 0.99 1.01 124.3" 126.'% 125.2% 1.4%
JNDENO(',Z.3-cd)PYRENE SOL BOL 0.80 1.06 0.78 131. 9"" 97.5% 114.7% 30.0%
DJBEN20(A.H)ANTHRACENE BDL BOl 0.80 0.99 1.01 123.~ 126.2% 125.1% ,.9%
BEN20(G.",I)PERYLENE BOL BDL 0.80 1.09 1. 12 136.0% 140.5% 138.2" 3.3%
# : SW 846 SPIKE CMPD. BOL = Below Detection Limits HIS = Not in Spike Mix * = Out of QC limits D = Detectable
RMPR Attachment D.lelil
~t~:;t d~
~ ._""
Outreach
Laboratory
31 I North Aspen
Broken Arrow. OK 7401 Z
[phone]
FAX [phone]
Client:
Client Project:
Lab Number:
Date Reported:
Date Received:
Page Number:
CASE NARRATIVE
Sequoyah Fuels
SF03-278
20030809
11124/03
10/21/03
lA of7
Three mise samples were received on 10/21/03. The samples were received in good condition and analyzed
for metals, uranium, thorium-230, ra-226 and percent moisture. On the original report issued 11121103, the
uranium result for sample number one "Press Only" was incorrectly reported. The sample had been diluted
and reran and converted in uglg. That correct result is included on the attached amended report. The
missing QC on many of the metals is due t~ insufficient sample volume.
lfyou have any questions, please call us at 918-251-2515.
Client: Sequoyah Fuels Corp.
Outreach Client Project: SF03·27H MISC RAFF·FIL TER
Laboratory Lab Number: 20030809
Date Reported: ] 112412003
31 I North Aspen
Broken Arrow, 01{ 740 12 Date Received: lO/21/0J
[phone] Page Number: lor6 FAX [phone]
Analytical Report
Method Result Units DL Prep Anlilysi!l Analyst
Dllte Date
Lah 10: 2UI/308119-1I1
Client 10: Press Only
Date Sllmplcd: 5/1/211113
Matrix: Other
Rluliochcrnical Anl,lysc. ..
Ra-226 SM 7500 Ra (M) 219 +/-8.08 pCi/g 1.42 11/12/2003 1111412003 RE
Th-230 LANLER200M 16200 +/-112 pCi/g 7,013 11/]012003 1111212003 RE
Uraniulll ASTM D 5174M 19400 uglg 1 11/5/2003 1111312003 RE
Inorganics Analyses
Percent Moislure LOD 57.4 'Yr. 10/2412003 CS
Phosphorus EPA 6010B 19600 mg/kg 144 10/2712003 11/2012003 CS
Metals Analyses
Aluminulll EPA 60 lOB 160000 mg/kg 530 1012712003 10/30/2003 CS
Antimony EPA6010B 78.4 mg/kg 5.88 1012712003 I0/2H12003 CS
Arsenic EPA6010B 3030 mg/kg 320 10/27/2003 10/30/2003 CS
Barium EPA GOlOB 4150 mg/kg 267 1012712003 10/30/2003 CS
Berylliulll EPA 60lOB 18.7 mg/kg 2.67 1012712003 10/28/2003 CS
Cadmium EPA (iOIOB BDL mg/kg 267 10/2712003 10130/2003 CS
Calciulll EPA 60 lOB 114000 mg/kg G4] 10/27/2003 10/30/2003 CS
Chromiull1 EPA 60 lOB 605 mg/kg 13,9 10127/2003 I ] 11812003 CS
Cobalt EPA6010B 133 mg/kg 3.74 10/27/2003 10128/2()03 CS
Copper EPA 60]OB 2360 mg/kg 3.74 10/2712003 10/28/2(0) CS
Tron EPA 60 JOB 164000 mg/kg 374 10/27/2003 10/3 \/2003 CS
Lead EPA 60]OB 1010 mg/kg 604] 10/2 7/2()O3 II/4/20()3 CS
Lilhiulll EPA 60 lOB BDL mg/kg 2.67 10/2 7/2003 IO/28120()3 CS
Magnesium EPA (i() I OB 7190 mg/kg 21.4 10/27/2003 10/30/2003 CS
Manganese EPA GOlOB 1930 mglkg 267 10/27/2003 l0!30/2003 CS
Mercury EPA 747lA 1.41 mg/kg 0.08 11111/2003 11/11/2003 CS
Molybdenum EPA 60 lOB 10700 mg/kg 18.7 10127/2003 11118/2003 CS
NickcJ EPA GOlOB 1660 mg/kg 320 10/2 7/2003 10!30/2003 CS
Potassi Lim EPA6010B 7740 mg/kg 2560 10/27/2003 J()/30/2003 CS
Selenium EPA GOlOB 348 mglkg 5.34 10/27/2003 10128/2003 CS
Silver EPA 60 lOB BDL mg/kg 90,8 10/27/2003 IO/30/2()03 CS
Sodium EPA GOlOB 7480 mg/kg 908 10127/2003 J()/3012003 CS
Strontium EPA 60IOB 1210 mg/kg ().41 10/27/2()()3 10/2!1/2()03 CS
Thallium EPA (jOIOB 5860 mglkg 25Hl ] O/27/2()03 10/30/2003 CS
Vanadium EPA 6010B BDL mg/kg 1.60 1012712003 1012812(0) CS
BDl. ~ Jlelow Deled ion J.imil
Client: ScquoYllh Fuels Corp.
Outreach Client Project: SF03-2n MISC RAFF-FIL TER
Lab Number: 20030809 Laboratory Date Reported: 11/24/2003
3 f f North Aspen Date Received: 10121/03 Broken Arrow, OK 740 f 2
[phone] Page Number: 2of6 FAX [phone]
Analytical Report
Mcthod Result Units DL Prell Anlllysis Anlllyst
Date DlIte
Zinc EPA 60 lOB BDL mglkg 751 10127/2003 10/3012003 CS
Lilli 10: 2U0308()I)-02
Client 10: PI-CNS Only Leachate
Date Sample!): 511120413
Matdx: Wlltcr
Radiochemiclil Analyses
Ra-226 SM 7500 Ra (M) 7.06 +/-8.15 pCil1 ] 5.3 1]/1212003 11/1412003 RE
Th-230 LANLER200M 80.1 +1-4l.7 pCi/1 70.4 II II 012003 11/12/2003 RE
Uranium ASTMD 5J74M 4.67 ug/l 1 1115/2003 11/13/2003 RE
Inol"l~llnics Analyses
Phosphonls EPA 60 lOB BDL mg/l 0.54 ] 11412003 1112012003 CS
Metals Analyses
AllIminum EPA 6010B 28.8 mgll 0_200 111412003 11/14/2003 CS
Antimony EPA 6010B BDL mg/I 0.220 11/412003 11/1412003 CS
Arsenic EPA 6010B 0.461 mgll 0.]20 1114/2003 11114/2003 CS
Barium EPA GOlOB BDL mgtl O.lOO 1114/2003 11114/2003 CS
Beryllium EPA 60lOB BDL mg/l 0.100 1 ]/412003 1111412003 CS
Cadmium EPA 6010B BDL mg/l 0.100 11/412003 11114/2003 CS
Calcium EPA 60 lOB 925 mg/I 2.40 11/412003 11119/2003 CS
Chromiulll EPA GOlOB BDL mg/I 0.240 11/412003 1l/14/2003 CS
Cobalt EPA 60 lOB 0.711 mg/l 0_080 111412003 11/1412003 CS
Copper EPA GOlOB 0.745 mg/I 0.080 11/412003 11114/2003 CS
Iron EPA 60 lOB BDL mg/l 0.140 ] 114/2003 11114/2003 CS
Lead EPA 60lOB BDL mgll 1.36 11/412003 11/14/2003 CS
Lithium EPA 6010B 0.464 Illgil 0.100 111412003 IlI14/20(J3 CS
Magnesiulll EPA 60 lOB 152 mgll (J .200 11/412003 ]]11812003 CS
Mangancsc EPA6010B 66.2 mg/l 0.100 11/412003 1111412003 CS
Mercury EPA 7471A BDL mg/l 0.0002 10/30/2003 11/11/2003 CS
Molybdenum EPA 60 lOB 13.3 mg/I 0.180 11/412003 1111412003 CS
Nickel EPA 6010B 8.86 mg/l 0.120 11/412003 1111412003 CS
Pollissium EPA6010B 203 mg/l 0.960 11/412003 11/14/2003 CS
SeleniUlll EPA 6010B BDL mg/I 0.200 11/412003 1111412003 CS
Silver EPA 60 lOB BDL mg/l 0.320 111412003 1111812003 CS
Sodium EPA 6010B 346 mg/l 1.70 1114/2003 IIIlS/2003 CS
Stronliulll EPA 60 lOB 2.81 mg/\ 0.240 11/412(}03 ]1114/2003 CS
Thallium EPA 6010B 0.418 mgll 0.220 11/412003 1I 114/2003 CS
Ill)!. = Below Detection Limit
Client: Sequoyah Fuels Corp.
Outreach Client Project: SF03-278 MISC RAFF-FIL TER
Lab Number: 20030809 Laboratory Date Reported: 11124/2003 311 North Aspen Date Received: JOI2I/03 Broken Arrow. OK 74012
[phone] Page Number: 30f6 fAX [phone]
Analytical Report
Method Result Units DL PIOel) Amllysis Anlilyst
Date Date
Vanadium EPA 6010B 0.320 mg/J 0.160 11/4/2003 11114/2003 CS
Zinc EPA 60]OB 2.92 mg/l 1.04 1114/2003 11118/2003 CS
211U3U8C1IJ-03
Press, Sludge, POI-tland Leachate
5/1/211113
Radiochemical Analyses
Ra-226 SM 7500 Ra (M) 9.96 +1-2.27 pCiIl 1.80 ] 1112/2003 11114/2003 RE
Th-230 LANLER200M 44.9 +1-12.2 pCi/1 15.0 1111012003 11/12/2003 RE
Uranium 4.53 ugll 1 1115/2003 11113/2003 RE
Inorganics Analyses
Phosphoms BDL mgll 0.54 11/412003 11120/2003 CS
Metals Analyses
Aluminum 7.82 mgll 0.200 11/4/2003 11114/2003 CS
Antimony BDL mg/l 0.220 11/4/2003 1111412003 CS
Arsenic EPA 6010B 0.170 mg/l 0.120 11/412003 1111412003 CS
Barium EPA 60 lOB 0.282 mgfl 0.100 111412003 1 III 4/2003 CS
Beryllium EPA 6010B BDL mt/l 0.100 11/4/2003 1111412003 CS
Cadmium EPA 60 JOB I"l'!gll 0.100 ] 1/412003 1111412003 CS
Calciulll EPA 60 lOB mgll 1.20 11/412003 11/1812003 CS
Chromium EPA 60 lOB 0.240 111412003 1111412003 CS
Cobalt EPA 60 lOB 0.080 111412003 1111412003 CS
Copper EPA 6010B 2.64 1 I/412003 11/1412003 CS
Iron EPA 6010B BOL ] 114/2003 11114/2003 CS
Lead EPA 60 lOB BDL 1114/2003 11114/2003 CS
Lithium EPA 60 JOB BDL mg/l 11114/2003 CS
Magnesium EPA6010B BDL mg/l 11114/2003 CS
Manganese EPA 6010B BOL mg/I 11114/2003 CS
Mercury EPA 7471A BOL mg/J 1111112003 CS
Molybdenum EPA 6010B 35.5 mg/1 0.180 11114/2003 CS
Nickel EPA 60 lOB 0.207 mg/J 0.120
Potassium EPA6010B 211 mg/I 0.960
Selenium EPA 60 lOB BDL mg/l 0.200 11/4/2003
Silver EPA 60 lOB BDL mg/I 0.320 11/4/2003
Sodium EPA 60l0B 199 mg/l 0.680 111412003
Slrontium EPA 60 lOB 4.21 mg/I 0.240 1114/2003
BDL = Below Dclcclioll I..imil
,~ ~ .. )~ .. ~ ._~.I'
Outreach
Laboratory
311 North Aspen
Broken Arrow, 01< 74012
[phone]
FAX [phone]
Porllmeter
Antimony
Arsenic
Barium
Beryllium
Cadmiulll
Calcium
Cohalt
Corrcr
Manganc~c
Mer~lIry
Nickel
Percent Moisture
Potassium
Ra-226
Selenium
Sodium
Strontium
Th-230
Thallium
Zinc
BDL = Below J)etc~1ioJl Limit
Blonk LCS
%REC
BOL 118.0
EO!.. 97.0
BOL 97.0
BOL 101.0
BOL IOLO
BDL 102.0
SOL 110.0
BOL 100.0
0.527 100.0
DOL 94.0
DOL 103.0
BDL 10G.0
0+/-0 158.0
1.48 93.0
142 119.0
BDL 9(;,0
0+1-0.2 92.8
5,34 92.0
BDL ]05.0
Client:
Client Project:
Lab Number:
Date Reported:
Date Received:
Page Number:
QC Report
LCSD DUP MS
%REC RPD RPD %REC
1<2.0
84.0
I(G.O
87.0
00
DO
1<6.0
8;;.')
10KO
96.0
88.0
100.0
DO
88.0
DO
K9,0
no
DO
QA Alllll"Oval:
Sequoyah Fuels Corp,
SF03-278 MISe RAFF-FIL TER
20030809
11/2412003
10121/03
o ofo
MSD Dntc
%REC RPD
72.0 13.5 10/2S/2(0)
1<5.0 J.G 10128/2(0)
89.0 3.8 10/21(/2003
91.0 4.5 10/28/2003
DO 1012812003
IX) 10128/2003
74.0 14.3 10/2812003
77.0 IO.S 10/28/2003
101.0 G.G 1f)/28/2003
104.0 !(O 11/11/2003
77.0 13.0 10/2812003
1012412003
DO 10/28/2003
11/1412003
n.o 4,5 10/2K!2003
DO 10121</2003
94,0 5.0 JO/2S/2003
1 J1I2/2003
DO 10/28/2003
DO 10/30/2(0)
RMPR Attachment 0 .1 civ
It!tf!. .v;~
Outreach
Laboratory
3 1 1 North Aspen
Broken Arrow. OK 74012
[phone]
FAX [phone]
March 13,2006
Scott Munson
Sequoyah Fuels Corp.
Hwy 10 & I-40
Gore, OK 74435 ) 1
PROJECT: SF05~'7K C
OUTREACH LAB ID: 20050975
Dear Mr. Munson:
Please find enclosed the analytical report for your samples received in our laboratory on
December 02, 2005 for the above captioned project. Eight soil samples were received in
good condition and analyzed for Uranium, Ra-226 and Isotopic Thorium, (added per client
request on 02/07/06).
The samples analyzed for isotopic thorium were acid digested and diluted to a known
volume. Aliquots were taken from the digestate and analyzed for Th232, Th230 and Th228.
The Th230 activity was very high. This resulted in a very small sample size being used for
the analysis.
All Quality Control for the requested analyses is reported on the analytical report. The
method blank, laboratory control standard and matrix spikes and spike duplicates for all
analyses were within method control limits.
These samples will be returned to you.
Thank you for choosing Outreach Laboratory and if you have any questions, please call us
at918-251-2515.
Laboratory Director
ODEQ 10 #9517 CERT. ID #OKOOI
NRC ODEQ LIe. #27522-01
Client: Sequoyah Fuels Corp.
Client Project: C;f~.,~~g Raffinate Dewatering
Lab Number: 20050975
Date Reported: 3113/06
Outreach Date Received: 12/2/05
laboratory Page Number: lof3
311 North Aspcn am'ten Arrow. 01( 74012
(918) 251·2515
fAX (918) 2.51·000s Analytical Report
Method Result Units DL Prep Analysis Analyst
Date Date
Lab IV: 20050975·01 r{~ l h 1'I.::1e 6rrf()1'1*< C.el) II-Client 10: 80256
Date Sampled: 11114/05 10:50:00 AM
Matrix: Soil
Radiochemical Analyses
Ra-226 SM 7500 Ra (M) 135 +/-3.96 pCi/g 0.605 12120/05 12/27/05 SD
Th-228 LANL ER200 M 730 +/-253 pCi/g 153 3/6/06 317106 RE
Th-230 LANL ER200 M 48100 +/-2060 pCi/g 1770 3/6/06 317106 RE
Th-232 LANL ER200 M 2170 +/-411 pCi/g 75 3/6/06 317106 RE
Uranium ASTM D 5174M 10100 ug/g 0.980 12/21/05 1112/06 MD
Lab 10: 20050975-02
Client 10: SD257 t;."iMI< ~~<;Ih &1/$
Date Sampled: 11/14/05 11:20:00 AM
Matrix: Soil
Radiochemical Analyses
Ra-226 SM 7500 Ra eM) 248 +1-5.90 pCi/g 0.546 12/20/05 12/27/05 SD
Th-228 LANL ER200 M 565+1-213 pCi/g 108 3/6/06 317106 RE
Th-230 LANLER 200 M 56600 +1-2160 pCi/g 1720 3/6/06 3/7/06 RE
Th·232 LANL ER200 M 2050 +/-390 pCi/g 82 3/6/06 317106 RE
Jranium ASTM D 5174M 10400 uglg 1.00 12/21/05 1112/06 MD
Jab 10: 20050975-03 a <
~lient ID: SD 258 ~. 1+6 4"f'd"ill< Ce I) (! ...
late Sampled: 11114/0511 :30:00 AM
1atrix: Soli
Radiochemical Anillyses
a-226 SM 7500 Ra (M) 176 +1· 5.09 pCi/g 0.888 12/20/05 12/27/05 SD
h-228 LANLER200 M 452 +1-203 pCi/g 140 3/6/06 317/06 RE
1·230 LANL ER200M 43900 +/. 1970 pCilg 1740 3/6/06 317106 RE
1-232 LANL ER200 M 1060 +1-287 pCi/g 68 3/6/06 317/06 RE
'anium ASTM D 5174M 809() uglg 0.952 12/21/05 11\2/06 MD
bID: 20050975·04 ~
lent 10: SD 259 /2( .4 )1l.b &rr(liSi ~ &1/ !J
te Sampled: 11114/0511 :40:00 AM
Itrix: Soil
Radiochemical Analyses
226 8M 7500 Ra (M) 332 +1· 6.75 pCi/g 0.551 12/20/05 12/27/05 SD
228 LANL ER200 M 761 +1· 260 pCi/g 121 3/6/06 317106 RE
230 LANL ER200 M 70 I 00 +/-2520 pCi/g 1840 3/6/06 317106 RE
)t. = Below Detectioll Limit
Client: Sequoyah Fuels Corp.
Client Project: Raffinate Dewatering
Lab Number: 20050975
Date Reported: 3113/06
Outreach Date Received: 12/2/05
Laboratory Page Number: 20f3
31 1 Nortl\ Aspen
6rol<£:n AllOW, at< 7/10 12
[phone]
FJ\,'{ (916) 2SI·0OO8 Analytical Report
Method Result Units OL Prep Analysis Analyst
Date Date
Th-232 LANLER200 M 2360 +1-443 pCi/g 73 3/6/06 3/7106 RE
Uranium ASTM D 5174M 8750 ug/g 0.990 12/21/05 1112106 MD
Lab 10: 20050975·05, "-E Client ID: SD260 jr:..lKlI".b &ny~ (i fl.. (JIZ. II
Date Sampled: 11114/05 I :20:00 PM
Matrix: Soil
Radiochemical Analyses
Ra-226 SM 7500 Ra (M) 266+1-5.71 pCi/g 0.567 12/20105 12/27/05 SD
Th-228 LANL ER 200 M 450 +1-192 pCi/g 119 3(6(06 3/7/06 RE
Th-230 LANL ER200 M 44500 +/-1900 pCilg 1580 3/6/06 3/7/06 RE
Th-232 LANL ER 200 M 2120 +/-393 pCi/g 90 3/6/06 3/7/06 RE
Uranium ASTM D 5174M 7080 ug/g 0.833 12(21105 1/12/06 MD
Lab 10: 20050975-06 &"f-!S" ~ (P f f F Client 10: SO 261 ~~·.a'J1A.t
Date Sampled: 11114/05 1:30:00 PM
Matrix: Soil
Radiochemical Analyses
Ra-226 SM 7500 Ra (M) 367 +1-6.55 pCi/g 0.601 12/20/05 12/27/05 SD
Th-228 LANL ER200 M 1080 +1-268 pCi/g 100 3/6/06 317106 RE
Th-230 LANL ER200 M 61800 +1-2070 pCi/g 1460 3/6/06 317106 RE
Th-232 LANL ER 200 M 2800 +/-424 pCi/g 87 3/6/06 317/06 RE
Uranium ASTM D5174M 7730 ug/g 0.806 12/21/05 1/12/06 MD
Lab ill: 20050975·07 It, tn-f()J} '7.t.. ~ ;; 4 Client ID: SO 262 ~c. ~
Date Sampled: 11114/051:35:00 PM
Matrix: Soil
Radiochemical Annlyscs
Ra-226 SJY1 7500 RIl (M) 180 +/~ 4.27 pCi/g 0.6\7 12/20/05 12/28/05 SD
Th-228 LJ\NL ER 200 M 111 0,+/-332 pCi/g 175 3/6/06 3/7/06 RE
Th-230 LANL ER 200' M 7440q +/-2100 pCi/g 1840 3/6/06 317106 RE
Th-232 LANL ER 200 M 4<)90 +1. 671 pCilg 72 316/06 3/7/06 RE
Uranium ASTM D5174M 8070 ug!g 0.909 12/21105 III 2(06 MD
Lab lD: 20050975-08 It C,/¥1t};~ tell /I Client JD: SO 263 Ii /VI6
I)ate Sampled: 11/14/051:45:00 PM
V1atrix: Soil
Radiochemical Analyses
BOL <= Below Dete~tion Limit
,~ Client: Sequoyah Fuels Corp.
Client Project: Raffinate Dewatering 4~!;~~' Lab Number: 20050975
Date Reported: 3!13f06
Outreach Date Received: 12/2/05
Laboratory Page Number: 30f3
311 North Aspen Broken Arrow, OK 74012
[phone]
FAX [phone] Analytical Report
Method Result Units DL Prep Analysis Analyst
Date Date
Ra-226 SM 7500 Ra (M) 166 +1-4.84 pCi/g 0.663 12/20/05 12128105 SD
Th-228 LANL ER200 M 449 +1-210 pCilg 144 3/6/06 3/7/06 RE
Th-230 LANL ER200 M 46200 +1-2090 pCi/g 1790 3/6/06 3/7106 RE
Th-232 LANL ER200 M 1700 +1-37.6 pCi/g 66 3/6/06 317106 RE
. Uranium ASTM D 5174M 8060 uglg 0.935 12/21/05 \/12/06 MD
QC Report
Parameter Blank LCS LCSD DUP MS MSD Date
%REC %REC RPD RPD %REC %REC RPD
Ra-226 0+1-0 122.0 112.0 8.8 23.9 1090 122.0 11.5 12/26/05
Th-230 0+1-0,1 141.0 101.0 324 NC 133.0 120.0 6.1 2/10106
Th-232 0.1+/-0 119.0 9S 9 212 NC 107.0 103.0 03 211 0/06
Uranium SOL 87.4 87.9 0.6 3.2 104.0 1080 3.4 12/30/05
Lab App,oval, ~
BOL = Below Detection Limit
RMPR Attachment D.lcv
Outreach
Laboratory
311 North Aspen
Broken Arrow, OK 74012
(9t8) 251-2515
FAJ«918)25J~
ft) ~~~~~~Ti1~YON ~ BUREAU 'tU..~pl
'b.: /\ (ClIEDr TED ~
Certificote'# L 2234 Testing
Case Narrative
Lab No: 20121449
.~.~. ~ fffieJ " .C·(
IIJ 01<001
This report contains the analytical results for the 1 sampJe(s) received under chain of custody by Outreach Laboratory on
12/11/12 II :40:02. These samples are associated with your SF12-387 project.
The analytical results included in this report meet all applicable quality control procedure requirements except as noted below:
The test results in this report meet all NELAC requirements unless noted below:
This report shall not be reproduced, except in full, without the written approval of Outreach Laboratory.
All radiochemical sample results for solids are reported on a dry weight basis with the exception of tritium, carbol1-J 4 and
radon, unless wet weight was requested by the client.
Observations / Nonconformances
The following QC parameters are outside method control limits:
The MS/MSD % Recovery for Arsenic and Barium diluted out.
Observations I Nonconformances
This sample exceeds are disposailimits and will be returned.
'NELAC Certified Paramctcr SDL = Below Detection Limit Pngc ! 01'3
Client: Sequoyah Fuels Corp
Client Project: SF1 2·38i
Lab Number: 2012144 S
Date Reported: 1'2121/12
Outreach Date Received: ! 2/! ! II:~
Laboratory Page Number: :2 01'3
311 North Aspen
Broken Arrow. OK 74012
(918) 251·2515
FAX [phone] Analytical Report
Method Result DL Units Qual. Prep Analysis Analyst
Date Date
Lab 10: 20121449-01
Client ID: SD-282
Date Sampled: 12/1011211:30:00
Matrix: SCM
Metals Analyses
Arsenic EPA 6010B* 1280 11.0 mglkg 12/18112 12119/12 RE
Barium EPA 601OB* 1530 5.50 mg/kg 12/18112 12/19/12 RE
Cadmium EPA 60 lOB * 1.03 0.50 lng/kg 12118/12 12/19/12 RE
Chromium EPA 601OB* 251 1.00 mg/kg 12/18/12 1211 9/12 RE
Lead EPA6010B* 361 1.00 mglkg 12118112 12/19/12 RE
Mercury EPA 7470A*/7471A* 1.76 0.168 mg/kg 12/11112 12/12/12 RE
Selenium EPA 6010B* 97.9 1.00 mglkg 12/18/12 12/19/]2 RE
Silver EPA 6010B* BDL 1.00 mglkg 12/18/12 12119/[2 RE
TCLP·Arsenic EPA 131116010B* 0.097 0.095 mg/I 12112/12 12/18112 RE
TCLP-Barium EPA 131116010B* BDL 0.098 mg/I 12/1211 2 12/18/12 RE
TCLP·Cadmiul11 EPA 131116010B* BDL 0.100 mg/I 12/121l2 12/18/12 RE
TCLP-Chromium EPA 131l/601OB* 0.202 0.100 mg/\ 12/12/12 12/18112 RE
TCLP-Lead EPA 1311160108* BDL 0.100 mg/! 12/12/12 12/18!! 2 RE
TCLP·MerclIry EPA 131117470A* 0.0003 0.0004 mg/I 12/19/12 12120112 MJ
TCLP-Seleniul1l EPA 13 111601 OB* BDL 0.140 rug/I 12/12112 12/18/12 RE
TCLP-Silver EPA 131 1/6010B* 0.238 0.121 rug/I 12112112 12/18/12 RE
*NElAC Certified Parameter BDL = Below Detection Limit Page 201'3
Outreach
Laboratory
311 North Aspen
Broken Arrow, OK 74012
[phone]
FAX (918) 251·0008
P:lramctcr
Arsenic
Barium
Cadmium
Chromium
Lend
Mercury
Selenium
Silver
TCLP·Arsenic
TCLP·Barium
TCLP·CmJmiunl
TCLP·Chromium
TCLP-Lead
TCLP-Mercury
TCLP-Selenium
TCLP·$ilver
*NELAC Certified Parameter
Client:
Client Project:
Lab Number:
Date Reported:
Date Received:
Page Number:
QCReport
Blank LCS LCSD DUP RER,NAD
%REC %REC RPD RPD orDER
0.400 101.0
0.010 91.4
0 99.2
0 87.4
0.100 86.3
BDL 99.0
0 98.0
0.200
-0.006 105.0
0.006 104.0
0 111.0
0.020 111 .0
0 105.0
0.000 93.0
0.005 105.0
0 84.2
Lab Approval:
BDL = Below Detection Limit
MS
%REC
DO
DO
83.9
88.0
94.9
70.7
93.8
85.2
105.0
102.0
107.0
11 1.0
103.0
92.0
102.0
82.8
MSD
Sequoyah Fuels Corp
SFI1-3Si
2012144S
12/21/12
12/1 1112
Date
%REC RPD
DO 3.4 121J9/12
DO 13.3 12/19/12
82.9 1.4 1211 9/1 2
85.5 0.9 12/19/12
85.1 2.4 12/19/l2
86.8 7.4 12112/12
96.6 l.4 12/19112
86.8 13.4 12119112
105.0 0.2 12/18/12
101.0 1.2 12/18112
108.0 0.4 12/18/12
110.0 1.2 J 211 8/12
103.0 0.6 1211 8/12
88.6 3.9 12/20/12
103.0 0.6 121J 8112
83.0 0.2 12/18112
Outreach Laboratory Icompany ObZJt l/Vrtt7r .&=V~ RrlJchiJ/1l b"1'oJ/4 r1." s/lJllllard. or
74012
[phone]
[phone] . -,'ft' IQ' , { Fax: ------------------~ _______ State 2:ip ______ -I
I RELINQUISHED BY DATE TIME RECEIVED BY: DATE TIME
My signature on this chain of custody form indicates that I am authorized by lIle above company to release samples for analysis. The company agrees to pay
the entire balance upon receipt of sample data and it is understood and agreed that any balance carried over thirty (30) days is subject to a 1.5% per month
(1 8% per annum) late charge. In the event of default, the company becomes legally liable for any reasonable attomey and/or collection fees and all related
costs necessary to remit the entire balance to OutreachTechnologies, Inc. (Outreach Laboratory) .
• Additional charnes apply for non-standard tum-times and EDD formats, for hardcopies, Level 4 data pl(9S, and radioactive sample disposal or return
Remarks (i.e.
Filtered, Unfiltered,
RMPR Attachment O.lcv;
Outreach
Laboratory
31 I North Aspen
Broken Arrow, OK 7401 2
[phone]
FAX [phone]
li LABORATORY ~
.. ,ACCREDITATION l%.:..r
0
0 BUREAU ..... "6J.v _ '-n·~1)rUJJ1 y '
i: 'o°rtlfi c.Jte # L :2284 T estll1g
net 0
tlJ OK001
Case Narrative
Lab No: 20130697
This report contains the analytical results for the I sample(s) received under chain of custody by Outreach Laborator} on
U6 :28 13 I 1:59:050 These samples are associated with your SF 13-128 project.
The analytical results included in this report meet all applicable quality control procedure requirements except as nOled beIO\\'
The test results in this report meet all N ELAC requirements unless noted below:
This report shall not be reproduced, except in full, without the written approval of Outreach Laboratory.
A" radiochemical sample results for solids are reported on a dry weight basis with the exception of tritium, carbon-14 and
radon . unless wet weight was requested by the client.
Observations / Nonconformances
The following QC parameters are outside method controllimirs:
rhe MS MSD DOD Recovery for Ammonia diluted out.
I he MS 00 Recovery for Nitrate diluted out.
AOI 00 Aelnw Detection Limit
Client: Sequo)ah Fut'l~ Corp
Client Project: Sf13-128
Lab Number: 20 I 30697
Date Reported 07 19 13
Outreach Date Received: 628 13
Laboratory Page Number: :2 of2
3 1 I North Aspen
Broken Arrow. OK 74012
[phone]
FAX [phone] Analytical Report
Method Result DL Coits Qual. Prep Analysis Anal)SI
Date Dille
Lab 10: 20130697-01
Cli~ol 10: SO-282
Oute Sampled ' 12110/1311:30:00
Matrix: SCM
Inorganics Analyses
Ammonia as N SM 4500-NH3 B-D 5210 84 mglkg 07'17 13 07 17 13 RI
Fluoride SFClKerr-McGee 44100 3070 mglkg 07 17 13 07 19 13 RT
257-F-3 SM 4500-F -
C
Nilrate -Nitrile as (N) SM 4500-N03-D 4580 75 mglkg 07 17 13 07 17 13 11.1
QC Report
Pllrnmeler Blank LCS LCSD DlJP RER. NAD MS MSD Date
%REC %REC RPD RPD or DER %REC %REC RPD
\ III 11 11lllld .I, N 0.1 1.0 DO DO 2.<1 07 17 L1
I IUllridt: 36.5 85.1 3.7 07 19 I ~
\;Iralt: N,lnlt: as (N) J 8 107.0 10.& DO 07 17 IJ
Lab Approval:
'NI LAl (crlir,~d Paramder BDL = Below Detection Limit I'age :. 1I1 ~
CHAIN OF CUSTODY
-, ~ .. ~ ~.~~~ d~
.,. ... IT
... -' Outreach Laboratory
;{*i."""i@-4-Z'"'"·l----·-: --;-, .......... ··-.... :2-·.., .. ...-' -.~ .... --!""~"--;;::;,,...'"-;;= ..... ~.,...~=.=?2""',.~~.,.." .. ~..,~""'t~-W~· .. '{""..;, -:~-:J
Company ,5GQt/Cy4tI£ ()Gi-S
=111111'10 11. 01 .. ,oj..--: ~ ~:;ti_4 ! ~
PO# Send by mail or email k.~dr:h;lIf! b~r"'IIJ f}.r. SldJ,dar"J.
311 North Aspen
Broken Arrow, OK 74012
Phone:
Fax:
[phone]
[phone]
yvww.outreachiab.com
~ .-~
Project:
Requested Turnaround Time~~
Sample/cooler Return address*?
Company ____ .. _____________ _ -Name
AddrE:iS
City CjGCG:
--==='=r-rM....,....-A Name Zi7''5!?f IAddrlJS-"i __ _ State G/<-
Phone Fax; ~ Cit)r State Zip
Data Email oniy
I Email address
.sE/3'-~2 _
?1"-ilI3 _
Hardcopy LvI 2 or LvI 4'" EDD" Phone
-~-. -. -----_. _ . ..JEmail.address ~!: a .'J r:' _ ._ -)
... J.I ' . .I=--~~ -. ~~~~" ~ '->--'-..31 ~_., ~ L-~ r -l'-1-. • ,~t.~~,~ .' 110-'.,-f= -p ..
~-Container Preservative # 'I? I T
.S: Size 1. ir:o <4 C t ' flj .-•. "} ~ Plastic or L. HNO,. pH.:,. 8 Glass 0. Hl:: ~I !<2 .. I ~1=l:: 4. rl",,,'(.,..l4 pH<L ~ I
5. NaGH pH>1 ! 'S. "-
-
g,,,mp!er '.Ionature A. /.I -~.-, '-//~
B.None \ r
I'~ ~-\ I
'";> '" \\
Remarks (Le.
Client S"mplc 10
5[)-2£:I-
"'7 I Date ~e
Sampled I Sampled I Matrix '" 'c;;;., 1 -""'" I I Filtered, Unfiltered,
Grab. Composit,,·
I5iD74 //:.1D).$ I I : P ---.k_--1 E~ >:t . i-l-=-F -F I '~~ I I I =r-= I I I -, ! I =±r--'~~. r :,! -t ii i 1 1 ! r --r--:RhFP,v11ti '
h?LtI D§ e ----l ~: ! I I ! I ! -\=-i=i=--I-_"
.: . 1--1 i I ! . l I ,,sIFE-SFJ2
1 3.,8'7, 5F/il
I t-----i--,
I "
I ;3?K
I I r-I i -!--~-I--r lREtv..eN-tO
-r $.&'c..
I J ___ Jc--.
RELINQUISHED BY ?~M~C: 37Zf./ DATE .IQ/~ TIMEI03PRECEI~~D ~'~ ~/~ t Ii;.. C/r,)Ji"", fl3 -j-iSil /
.... y'" ..' TIME .1
CualO6l Seal. 11l1,,.:IL """V";';; N
I My signature on this chain of r.ustody form indicates that I am authorized by the above company to release samples for analysis. The company agreefi to pay Cou"" TMn;lCl1Ol>, ... ; NA-
the entire balance upon receipt of sample data and it is understood and agreed thai any balance carried over thirty (30) days is subject to a 1.5% per month "} 11 ~(')I..;1·
, (18% per annum) late charge. In the event of default, the company becomes legally-liable for any reasonable attorney andior colieciion fees and all related l .,·j, project ('>eP"'-.,J!.-.J.it;{-_ I costs necessary to remit the entire balance to OutreachTechnologies, Inc. (Outreach Laboratory).'-. .
. -Additional charges apply for non-standard turn-times and EDD frJrmats, for hardcopies, Level 4 data pkgs, and radioactive sample disposal or returned Pnl'l(' of I
RELINQUISHEO In-____ _ OATF I ME RECF.IVeO BY: Dt,Tf-CJME
AMPA Allachmenl E.4a
JON S. CORZINE
Governor
Donna Eidson
Outreach Laboratory
311 N. Aspen Avenue
Broken Arrow. OK 74012
Dear Ms. Eidson:
Ae: Corrected ACPL
Jibth of ~~fu 31~r9~g
DEPARTMENT OF ENvIRONMENTAL PROTECI'ION
Office of Quality Assurance
401 Bost State Street, 2"rI Floor, P.O. Box 424
Trenton, NewJeraey 08625
Telephone: [phone]
Facsimile: (609) 777·1774
August 3, 2009
Laboratory Certification 10# OK001
Mark Mauriello
Acting Commissioner
A corrected Fiscal Year 2010 Annual Certified Parameter List (ACPL) that reflects the current
status of your facility is enclosed. If there are any discrepancies, please contact your Laboratory
Certification Officer to verify information and make arrangements for a new ACPl. .
As always, we are available to discuss any comments or questions. Please do not hesitate to
contact your laboratory certification officer or me.
Sincerely,
Joseph F. Aiello, Chief
New Jersey is an Equal Opportunity Empluyer • Printed on Recycled Paper and R£cyclable
New Jersey Department of Environmental Protection
National Environmental Laboratory Accreditation Program
ANNUAL CERTIFIED PARAMETER LIST AND CURRENT STATUS
Effective as of 07/01/200' until 0613012010
Laboratory Name: OUTREACH LABORATORY Laborjitory Number: OKOOI Activity ID: NLC090001
31lNASPEN
BROKEN ARROW, OK 74011
Category: SDW07 -Radlochem.: Radioactivity I Radiollucllde
Eligible to
Report
Status NJData State Code Matrix
Certified Yes NJ SDW07.01000 DW
Certified Yes NJ SOW07.01001 OW
Certified Yes NJ SOW07.03000 DW
Certified· Yes NJ SOW07.03100 OW
Certified Yes NJ SOW07.03900 OW
Certified Yes NJ SOW07.04100 OW
Certified Yes NJ SDW07.0S000 OW
Certified Yes NJ SDW07.06010 DW
Certified Yes NJ SOW07.07000 OW
Certified Yes Nl SOW07.08200 ow
Category: SDW08 -Radon in Drinking Water
Eligible to
Report
SllItns NJDllta State Code Matrix
Certified Yes NJ SDW08.01000 OW
Category: SHW01-Characteristics of Hazardous Waste
EligIble to
Report
Status NJDatu State Code
Certified Yes NJ SHW02.069S0
Catogory: SHW04 -Inorgulc Parameters
ElIgible to
Report
Status NJ Data State Code
Certified Yes NJ SHW04.OlS00
MntrIx
NPW
Matrix
NPW
Technique Descl'iption Approved Method
Proportklnal or Scintillation [EPA 900.0]
48-Hour Rapid Gross Alpha Test [OTHER N. J. A. C. 7:18-6J
Gamma Spectrometry -Radiochemistry [EPA!JOl.O]
Gamma Spectrometry [EPA 901.1]
Radiochemical [SM 7S00-Ra 8}
Precipitation [EPA904.0}
Precipitation [SM 7S00 -Ra B]
Strontium 90 [EPA 905.0]
Distillation/Liquid Scintillation [EPA 906.0]
Laser Phosphorimetry [ASTM D5174-91]
TeclutittuC! DesttlpHnll.. Approved Method
Liquid Scintillation [SM 7500-RnJ
Teclmlque Description Approved Method
TCLP, Toxicity Procedure, Shaker [SW-846 1311]
Technique Description Approved Metbod
Acid Digestion! Aqueous Samples, rcp. FLAA [SW-846 30 lOA, Rev. 1,7/92]
KEY: AE ~ Air and Emissions, BT'" Biological Tissues, OW = Drinking Water, NPW = NOll-Potable Water, SCM = Solid 81ld Chemical Materials
-Annual Certified ParametelS Ust -Effective as of 0710112009 until 0613012010
Parameter DescrIption
Gross -alpha-beta
S~···D.-'~ /'Q~ ~ ~~ '" .~.
''If} . ~"Y 'I( h 0 ft ,y
Gross -alpha (incl. radium &. U excl. radon)
Cesium 134/137
Gamma emitters
Radium-226
Radium-228
Radium -total
Strontium· 90
Tritium
Uranium
Parameter DeSO'lpfiQU
Radon
Parameter Description
Semivolatile organics
Parameter Description
Metals, Total
Page I of12
New Jeney Department of Environmental Protection
National Environmental Laboratory Accreditation Program
ANNUAL CERTIFIED PARAMETER LIST AND CURRENT STATUS
Effective as of 071OV2009 until 06/30/2010
Laboratory Name: OUTREACH LABORATORY Laboratory Number: OKOOl Activity ID: NLC090001
311NASPEN
BROKEN ARROW, OK 74012
Category: BHWOS -Organic Parameters, Prep. I Screening
Eligible to
Report
Status NJData State Code Matrix Tcclmique Description Approved Method
Certified Yes NJ SHW05.01000 NPW Sepamtory Funnel Extraction ISW-846 3510C, Rev. 3, 12/96]
Certified Yes NJ SHWOS.07000 NPW Purge & Tmp Aqueous [SW-846 5030B, Rev. 2, 12/96]
Category: SHW06 -Orgrutlc .Parameters, Chromatography
Eligible to
Report
Status NJData State Code Matrix Technique Description Approved Method
Applied No NJ SHW06.12005 NPW Oc, Extraction, ECD or HECD, CapilJaI}' [SW-346 8081A]
Applied No NJ SHW06.12010 NPW Gc, Extraction, ECD or HEeD, CapiUaI}' [SW-34680S1A)
Applied No NJ SHW06.12020 NPW GC, Extraction, ECD or HECD, CapilJaI}' [SW-846 8081A]
Applied No NJ SHW06.12030 NPW GC, Extraction, ECD or HECD, Capillal}' [SW-846 SOSIA)
Applied No NI SHW06.12040 NPW Ge, Extraction, ECD or HECD, 'CapiUary [SW-846 8081A]
Certified Yes NJ SHW06.l2050 NPW GC, Extraction, ECD or HECD,'Capillary [SW-846 808IA, Rev. 1,12196]
Certified Yes NJ SHW06.l2060 NPW GC, Extraction, ECD or HEeD, Capillal}' [SW-846 808IA, Rev. 1, 12/96]
Applied No NJ SHW06.12070 NPW Ge, Extraction, ECD or HECD, 'Capillary [SW-846 SOSlA]
Applied No NJ SHW06.12080 NPW GC. Extraction, ECD or HEeD, CapiUaty [SW-846 S08tA]
Applied No NJ SHW06.12090 NPW GC, Extmction, ECD or HEeD, Capillary ISW-S46 SaBIA]
Applied No NJ SHW06.l2IOO NPW GC, Extraction, ECD or HEeD, Capillal}' [SW-846 SOSIA]
Applied No NJ SHW06.l2110 NPW Gc, ExtIllCtiOn, ECD or HEeD, 'Capillaxy [SW-846 BOBIA]
Applied No NJ SHW06.I2I20 NPW GC, Extraction, ECD or HECD, Capillal}' [SW-846 SOSIA)
Applied No NJ SHW06.12I30 NPW GC, Extraction, ECD or HEeD, Capillaty [SW-846 80BIA]
Applied No NJ SHW06.l2140 NPW Gc, Extractioll, ECD or HECD, Capillary ISW-846 SOBIA]
Applied No NJ SHW06.l2150 NPW GC, Extraction, ECD or HECD, Capillary ISW-846 80BIA)
Certified Yes NJ SHW06.12160 NPW OC, Extm:tion, ECD or HEeD, Capillary [SW-846 SaBIA, Rev. 1,12196]
Applied No NJ SHW06.l2170 NPW GC, Extraction, ECD or HECD, Capillal}' [SW-846808IA)
Applied No NJ SHW06.I2I80 NPW Gc, Extmetion, ECD or HECD, Capillary [SW-846808IA]
Certified Yes NJ SHW06.12190 NPW GC, Extraction, ECD or HECD, Capillary [SW-846 80S lA, Rev. I, 12196]
Applied No NJ SHW06.I2200 NPW GC, Extraction, ECD or HEeD, Capillary [SW-846 BOSIA1
Certified Yes NJ SHW06.12210 NPW Ge, Extlllctloa, ECD or HECD, Capillary [SW-846 BOBIA, Rev. I, 12196]
Certified Yes NJ SHW06.I2220 NPW GC, Extmction, BCD or HECD, Capillary (SW-846 808IA, Rev. 1, 12196]
Certified Yes NJ SHW06.l3110 NPW GC, Extraction, ECD or HEeD, CapiUary [SW-846 8082, Rev. 0, 12196]
KEY: AE = Air and Emissions, BT = BiologiCIIl Tissues, DW" Drinking Water, NPW = Non-Potable Water, SCM = Solid and Chemical Materials
-Annual Certified PalllmetelS List -Effective as of 07l0lJ2()09 until 0613012010
Parametcr Description
SemivoJatile organics
Volatile organics
Parameter Descril!tion
Alachlor
Aldrin
AlphaBHC
BetaBHC
DcltaBHC
Lindane (gamma BHC)
Chlordane (technical)
Chlordane (alpha)
Chlordane (gamma)
DOD (4,4'-)
ODE (4,4'-)
D.DT(4,4'-)
Dieldrin
Endosulfan I
Endosulliln II
Endosulfan sulfate
Endrin
Eadrin aldebyde
Endrin ketone
Heptachlor
Heptachlor epoxide
Methoxychlor
Toxaphene
PCB 1016
Page20f12
New Jersey Department of Environmental Protection
National Environmental Laboratory Accreditation Program
ANNUAL CERTIFIE][) PARAMETER LIST AND CURRENT STATUS
Effective as of :07101/2009 until 06/30/2010
Laboratory Name: OUTREACH LABORATORY Laboratory Number: OKOOI Activity ID: NLC090001
311N ASPEN
BROKEN ARROW, OK 74012
Category: SHW06 -Organic Parameters, Cbromatography
Eligible to
Report
Statu.s NJData State Code Matrix ~Tl!clmlqlle DesalplioQ Approved Method
Certified Yes NJ SHW06.13120 NPW GC, ExlIactioll, ECD or HECD, 'Capillary [SW-846 8082, Rev. 0, 12/96]
Certified Yes NJ SHW06.13130 NPW Ge, ExlIaction, ECD or HECD, Capillary [SW-846 8082, Rev. 0, 12/96]
Certified Yes NJ SHW06.13140 NPW GC, Extraction, ECD Of HECD, Capillary [SW-846 8082, Rev. 0, 12/96]
Certified Yes NJ SHW06.131S0 NPW Gt, ExlIaction, ECD or HEeD, Capillary [SW·S46 8082, Rev. 0, 12196]
Certified Yes NJ SHW06.13160 NPW Gc, Extraction, BCD or HECD, Capillary [SW-846 8082, Rev. 0, 12196)
Certified Yes NJ SHW06.l3170 NPW CC, Exbaction, ECD or HECD, Capillary [SW-846 80S2, Rev. 0, 12196]
Certified Yes NJ SHW06.23040 NPW GC, Extraction, ECD, Capillary [SW-846 81 S lA, Rev I, 9/96]
Certified Yes NJ SHW06.23060 NPW GC, Extraction. ECD, Capillary [SW-846 SIS1A, Rev 1,9/96]
CategOry: SHW07 -Orgllnie Parameters, ChromatographyJMS
Ellgible to
Report
Status NJData State Code Matrix Teclmlque Description Approved Method
Certified Yes • NJ SHW07_04010 NPW Gc/MS, P &. Tor Direot Injection, Capillary [SW-846 8260B, Rev. 2, 12/96]
Applied No NI SHW07.04011 NPW GClMS, P & T or Direct Injection, Capillary [SW-846 826OB)
Applied No NJ SHW07.04012 NPW GCJMS, P & T or Direct InjectioD, Capillary [SW-846 8260B]
Applied No NJ SHW07.04013 NPW GCfMS, P & T or Direct Injection, Capillary [SW-846 8260B)
Applied No NJ SHW07.04014 NPW GC/MS, P &. T or Direct lIijectioD, Capillary [SW·846 8260B]
Certified Yes NJ SHW07.04020 NPW GC/MS, P & T or Direct Injection, Capillary [SW·8468260B, Rev. 2, 12/96]
Applied No NJ SHW07.04022 NPW GCfMS, P & T or Direct Injection, Capillary [SW-S468260B]
Applied No NJ SHW07.04023 NPW OC/MS, P &. T or Direct Injection, CapillalY [SW-846 8260B]
Applied No NJ SHW07.04030 NPW GCIMS, P & T or Direct Injection, CapillalY [SW-846 8260B]
Applied No NJ SHW07.04040 NPW (jC/MS, P & T or Direct Injection, Capillary [SW·S46 &260B]
Certified Yes NJ SHW07.04050 NPW GCIMS, P &. T or Direct Injection, Capillary [SW-846 8260B, Rev. 2,12196]
Applied No NJ SHW07.04060 NPW GClMS, P &. T or Direct InjectiDn, Capillary [SW-8468260B]
Applied No NJ SHW07.0406S NPW CClMS, P & T or Direct Injection, Capillary [SW-846 8260B]
Applied No NJ SHW07.04067 NPW GClMS, P & T or Direct l1\iection, Capillary (SW-8468260B]
Applied No NJ SHW07.04070 NPW GClMS, P & T orDirect Injection, Capillary [SW-846 8260B]
Applied No NJ SHW07.04071 NPW GClMS, P & T or Direct Injection, Capillary [SW-846 8260BJ
Applied No NJ SHW07.04072 NPW GClMS, P & T or Direct Injection, Capillary [SW-846 8260B]
Applied No NJ SHW07.04073 NPW GC/MS, P & T or Direct Injection, Capillary [SW-8468260B]
KEY: AE= Air and Emissions, BT = Biological Tissues, DW = Drinking Water, NPW = Non-Potable Water, SCM '"' Solid and Chemical Materials
-Annual Certified ParamelelS List -Effective 08 of 0710 1/2009 until 06130/2010
Parameter ~criptiDlt
PCB 1221
PCB 1232
PCB 1242
PCB 1248
PCB 1254
PCB 1260
D (2,4-)
TP (2,4,S-) (Silvex)
Parameter Desui.ption
Benzene
Bromobenzene
Butyl benzene (n-)
Sec-butylbenzene
Tert-butylbenzene
Chlorobenzene
Chlorotoluene (2-)
Chlorotoluene (4-)
Dichlorobenzene (1,2-)
Dichlorobenzene (1 ,3-)
Dichlorobenzene (1,4-)
Ethylbenzene
Isopropylhenzene
l'Iopylbenzene (n-)
Toluene
Isopropyltoluene (4-)
Trichlorobenzene (1,2,3-)
Trimethylbenzene (I ,2,4-)
Page 3 of12
New Jersey Department of Envilronmental Protection
National Environmental Laboratory Accreditation Program
ANNUAL CERTIFIED PARAMETER LIST AND CURRENT STATUS
Effective 8S of 07/0112009 until 06/30/2010
Laboratory Name: OUTREACH LABORATORY Laboratory Number: OKOOI Activity ID: NLC090001
311N ASPEN
BROKEN ARROW, OK 74012
Category: SHW07 -Organic Parameters, Chrollll\tographylMS
Eligible (0
Report
Status NJDatn State Code Matrix Technig,ue Description Approved Metllod
Applied No NJ SHW07.04014 NPW CClMS, P & T or Dittet rqjection, Capillary [SW-846 826OB]
Applied No NJ SHW07.04075 NPW GClMS, P&T, or Direct Inj ection, Capillary [SW-846 826OC]
Applied No NJ SHW07.04080 NPW GClMS, P & T or Dittet Injection, CapiUaI}' [SW-8468260BJ
APplied No NJ SHW07.04081 NPW CClMS, P & T or Direct Injection, Capillary [SW-8468260B]
Applied No Ni SHW01.04082 NPW GC/MS, P & T or Direct Injection, CapiUaly [SW-8468260B]
Applied No NJ SHW07.04089 NPW GClMS, P & T or Direct Injection, Capillary [SW-8468260B]
Applied No NJ SHW07.04090 NPW GCIMS, P & T or Direct Injection, Capillary [SW-B46 8260B]
Applied No NJ SHW07.04095 NPW GC/MS, P & T or Dittet Injection, Capillary [SW-846 8260B]
Applied No NJ SHW07.04100 NPW GClMS, P & T or Direct Illjection, Capillal}' . [SW-8468260BJ
Certified Yes NJ SHW07.04I20 NPW GeIMS, P & T or Direct Injection, Capillul}' [SW-846 8250B, R~v. 2, 12/96]
Applied No NJ SHW07.04130 NPW GC/MS, P & T or Direct Il\iection, Capillary [SW-8468260B]
Applied No NJ SHW07.04140 NPW GClMS, P & T or Direct Injection, Capillary [SW-8468260B]
Certified Yes NJ SHW07.04150 NPW GCIMS, P & T or Direct [njection, Capillary [SW-B46 8260B, Rev. 2, 12196]
Applied No NJ SHW07.04160 NPW GC/MS, P & T or Direct IQ,jection, Capillary [SW-846 8260B]
Applied No NJ SHW07.04165 NPW GClMS, P & T or Direct Injection, Capillary [SW-846 8260B}
Applied No NJ SHW07.04170 NPW GClMS, P & T or Direct Injection, Capillal)' [SW-8468260B]
Applied No NJ SHW07.04180 NPW GCIMS, P & T or Direct Injection, Capillary [SW-8468260B]
Applied No NJ SHW07.04185 NPW GC/MS, P & T or Direct Injection, Caplllal}' [SW-8468260B]
Applied No NJ SHW07.04186 NPW GCIMS, P & T or Direct Illjection, Capillary [SW-8468260B]
Applied No NJ SHW07.04187 NPW GClMS, P &. T or Direct rnjection, Capillary [SW-8468260B]
Applied No NJ SHW01.04I90 NPW GClMS, P & T or Direct Injection, Capillary [SW-846 826OB]
Applied No NJ SHW07.04200 NPW GC/MS, P & T or Direct [njeclion, Capillary [SW-846 8260B]
Certified Yes I':IJ SHW07.04210 NPW GClMS, P & T or Direct Injection, Capillul)' [SW-846 8260B, Rev. 2, 12196]
Certified Yes NJ SHW07.04220 NPW GC/MS, P & T or Direct lojection, Capillary [SW-846 8260B, Rev. 2, 12196]
Applied No NJ SHW01.04230 NPW GClMS, P & T or Direct Injection, Capillal}' [SW-846 8260B]
Applied No NJ SHW07.04235 NPW GC/MS, P & T or Direct Injection, Capillary [SW-846 8260B]
Applied No NJ SHW01.04240 NPW GCIMS, P & T or Direct Injection, Capillal}' [SW-8468260B]
Applied No NJ SHW07.0424I NPW GeIMS, P & T or Direct Injection, Capillary [SW-8468260B]
Applied No NJ SHW07.04242 NPW GCIMS, P & T or Direct Injection, Capillal}' [SW-846 8260B]
Applied No NJ SHW07.04249 NPW GClMS, P & T or Directll\iection, Capillary [SW-846 8260B]
Applied No NJ SHW07.04250 NPW GClMS, P & T or Direct Injection, Capillary [SW-846 8260BJ
Applied No NJ SHW07.04270 NPW GC/MS, P & T or Direct Injection, Capillal)' [SW-8468260B]
KEY: AE = Air alld Emissions, BT ~ Biological Tissues, DW = Drinking Water, NPW = Non-Potable Water, SCM = Solid and Chemical Materials
-Annual Certified Parameters List --Effective as of 07/0112009 until 06/3012010
Parameter Description
Trimethylbenzene (1,3,5-)
Trimelliylbenzene (1,2,3-)
Xylenes (total)
Xylene (m-)
Xylene (0-)
Bromooblommethane
Bromodichlorometllane
Bromoetbane
Bromoform
Carbon tetmchloride
Chloroethan6
Chloroethyl vinyl ethcr (2-)
Chlorofonn
Chloromethane
Dietllyl ether (Ethyl ether)
Dichloropropene (truns-l,3-)
Dibl'Omochlol'Omethane
Dibromoetllane (1,2-) (EDB)
Dibromomethnne
Dibromo-3-chloropropane (1,2-)
Dichlorodifluoromethane
Dichloroethane (1,1-)
Dichloroethane (1,2-)
Dichloroethene (1,1-)
Dichloroethenc (trans-l,2-)
Dichloroethenc (c.is-l,2-)
Dichloropropane (1,2-)
Dichloropropane (1,3-)
Dichloropropane (2,2-)
Dichloropropene (1,1-)
Dicbloropl'Opene (cis-l,3-)
TetJachloroelhane (1,1,2,2-)
Page4or12
New Jersey Department of Environmental Protection
National Environmental Laboratory Accreditation Program
ANNUAL CERTIFIED PARAMETER LIST AND CURRENT STATUS
Effective as of 0710112009 until 0613012010
Laboratory Name: OUTREACH LABORATORY Laboratory Number: OKOOI Activity ID: NLC090001
311NASPEN
BROKEN ARROW, OK 74012
Category: SHW07 -Organic Pal"llmetcrs, ChromatograpbylMS
Eligible to
Report
SllifUS NJDllta State Code Matrix Teclmique Description. Approved Method
Certified Yes NJ SHW07.04280 NPW OC/MS, P & T or Direct Injection, CapilJal)' [SW-846 8260B]
Applied No NJ SHW07.04290 NPW GClMS, P & T or Direct Injection, Capillal)' [SW-846 8260B]
Applied No NJ SHW07.04300 NPW GCIMS, P & T or Direct Injection, Capillal)' [SW-846826()B]
Certified Yes NJ SHW07.04310 NPW GCIMS, P & T or Direct Injection, CapnJary [SW-846 8260B, Rev. 2, 12196]
Applied No NJ SHW07.04320 NPW GC/MS, P & T or Direct Injection, Capillal)' [SW-8468260B]
Applied No NJ SHW07.04322 NPW GCIMS, P & T or Direct Injection. Capillary [SW-846 8260B]
Applied No NJ SHW07.04325 NPW GClMS, P & T or Direct Injection. Capillary [SW-846 8260B)
Applied No NI SHW07.04327 NPW GClMS, P & T or Direct Injection, Capillal)' [SW-8468260B]
Certified Yes NJ SHW07.04330 NPW GClMS, P & T or Direct Injection, CapiUal)' [SW-846 8260B, Rev. 2, 12/96]
Applied No NJ SHW07.04340 NPW GClMS, P & T or Direct Injection, Capillary [SW-846 8260B1
Applied No NI SHW07.043S0 NPW GClMS, P & T or Direct Injection, Capillary [SW-846 8260BJ
Certified Yes NJ SHW07.04360 NPW GClMS, P & T or Direct Injection. Capillary [SW-846 826()B, Rev. 2, 12196]
Applied No NJ SHW07.0436S NPW GClMS, P & T or Direct Injection, Capillary [SW-846 8260B]
Applied No NJ SHW07.04370 NPW GClMS, P & T or Direct Injection, Capillary [SW-846 826()B]
Applied No NJ SHW07.04378 NPW GClMS, P & T or Direct Injection, Capillary [SW-846 8260B]
Applied No NJ SHW07.04380 NPW (lClMS, P & T or Direct Injection. Capillary [SW-846826()B]
Applied No NJ SHW07.04390 NPW GClMS. P & T or Direct Injection, Capilla1)' [SW-846 826()B]
Certified Yes NJ SHW07.04500 NPW GClMS, P & T or Direct Injection, Capillal)' [SW-846 8260B, Rev. 2, 12196]
Certified Yes NJ ·SHW07.04530 NPW GClMS. P & T or Direct Il\ieetion, Capillary [SW-846 8260B, Rev. 2,12/%1
Applied No NJ SHW07.04540 NPW GCIMS, P & T or Direct Injection, Capillary [SW-846 8260B]
Applied No NJ SHW07.04SS0 NPW GC/MS, P & T or Direct bijection, Capillln)' [SW-846 8260B)
Applied No NI SHW07.04560 NPW GClMS, P & T or Direct Injection, Capillary [SW-846826OBJ
Applied No NJ SHW07.04570 NPW GCIMS, P & T or Direct Injection, Capillary [SW-846 8260B]
Certified Yes NJ SHW07.04580 NPW GC/MS, P & T or Direct Injection, Capillary [SW-846 8260B, Rev. 2, 12196]
Applied No NJ SHW07.0459S NPW GClMS. P & T, Capillary Column
Applied No NJ SHW07.05006 NPW GClMS. Extract or Dir Inj, CapiJlary [SW-846 827OC]
Applied No NJ SHW07.05010 NPW GClMS, Extmct or Dir lnj, CapiUary [SW-846 8270C]
Applioo No NJ SHW07.0S030 NPW GClMS, Extract or Dir Inj, Capillary [SW-8468270C]
Applied No NJ SHW07.05038 NPW GCIMS, Extract or Dir Inj. Capillary [SW-846 8270C]
Applied No NJ SHW07.0S040 NPW GClMS, Exlnlct or DiT Inj, Capillary [SW-846 8270C]
Applied No NJ SHW07.05048 NPW GClMS, Extract or Dir Inj, CapiUaty [SW-846 8270C]
Applied No NJ SHW07.050S0 NPW GC/MS, Extract or Dir Inj. capillary [SW-846 8270C)
KEY; AB = Air and Emissions, BT = Biological Tissues, DW'" Drinking Water, NPW" Non-Potable Water, SCM = Solid and Chemical Materials
-Annual Certified Pal'BlnetclS List -Effective as of 07/0112009 until 06/30/20]0
Parameter Description
Tetrachloroethene
Trichloroethane·( 1,1,1-)
Trichloroethane (1,1,2-)
Trichloroethene
Trichlorofluorometbane
Trichloro (1,1,2-) lrifluoroelhane (1,2,2-)
Trichloropropane (1,2,3-)
Vinyl acetate
Vinyl chloride
Acetone
Carbon disulfide
Butanone (2-)
Ethyl acetate
Hexanone (2-)
N-Nitroso-di-n-butylamine
Pentanone(4-methyJ-2-)
Methyl tert-butyl ether
Hexachlorobutadieoe (1,3-)
HelCaChloroethane
Naphthalene
Styrene
Tetrachloroethane (l, 1,1,2-)
Trichlorobenzene (I ,2,4-)
Nitrobenzene
Gasoline range organic
N-Nitroso-di-n-propylomine
N-Nitrosodiphenylamine
Carbazole
Benzidine
Dichlorobcnzidine (3,3'-)
Aniline
Chlomniline (4-)
Page50fl2
New Jersey Department of Environmental Protection
National Environmental Laboratory Accreditation Progra~
ANNUAL CERTIFIED PARAMETER LIST AND CURRENT STATUS
Effelltlve as of {J7I01l2009 until {J6J30/101{J
Laboratory Name: OUTREACH LABORATORY Laboratory Number: OKOOI Activity ID: NLC09{)OOl
311 N ASPEN
BROKEN ARROW, OK 74012
Category: SHW07 -Organic Pal'ameters, ChromatograpllylMS
Eligiblcto
Report
Sta1~ NJData Stllte Code Matrix Tedw!lue Description Approved Method
Applied No NJ SHW07.05060 NPW GC/MS, Extract or Dir Inj, Capillary [SW-8468270C]
Applied No NJ SHW07.0S062 NPW GClMS, Extract or Dir Inj, Capillary [SW-8468270C]
Applied No NJ SHW07.05063 NPW GC/MS, &tlllct or Dlr l!\i, Capillary [SW-846 8270q
Applied No NJ SHW07.05070 NPW GClMS, Elltl1\Ct or Dir Inj, Capillary [SW-l!46 S270q
Certified Yes NJ SHW07.0S080 NPW GClMS, Extmct or Dir Inj, Capillmy [SW-846 8270C, Rev. 3, 12/96]
Applied No NJ SHW01 :05090 NPW GCIMS, Extl'llct or Dir Inj, Capillary ISW-l!46 8270q
Applied No NJ SHW07.05100 NPW GCIMS, Extract or Dir Inj, Capillary [SW-846 8270C]
Applied No NJ SHW07.05110 NPW GClMS, Extl'llct Ilr Dir Inj, Capntary [SW-8468270C]
Applied No NJ SHW07.05115 NPW GC/M8, Extl'llct or Dir lnj, CapiUary [SW-846 8270C]
Applied No NJ SHW07.05120 NPW OCIMS, Exlmct or orr Inj, Capillary [SW-l!46 8270C]
Applied No NJ SHW07.05130 NPW GClMS, Extl'llCt or Dir Inj, CspiUary [SW-846 8270C]
Applied No NJ SHW07.0S132 NPW GCIMS, Extl'llct Ilf Dir Inj, Capillary [SW-846 8270q
Applied No NJ SHW01.05140 NPW GClMS, Extmct or Dir Inj, Capillary [SW-846 8270C]
Applied No NJ SHW07.0S1S0 NPW GC/MS, Extract or Dir Inj, Capillary [SW-846 8270C]
Applied No NJ SHW07.05160 NPW GC/MS, Extract or Dir Inj, Capillmy [SW-846827OCI
Certified Yes NJ SHW07.05170 NPW GCIMS, Extract or Oir Inj, Ca~i11ary [SW-8468270C]
Applied No NJ SHW07.0S1S0 NPW GClMS, ExlIact or Dir In.i, CapUIaIy [SW-8468270C]
Applied No NJ SHW07.0SI90 NPW GC/MS, Extl'llct Ilr Dir Inj, Capillary [SW-8468270C]
Applied Nt) NJ SHW07 .05200 NPW OC/MS, Exttact or Dir lnj, Caplllary [SW-846 8270C]
Applied No NJ SHW01.05210 NPW GClMS, &tJact or Dir Inj, Capillary [SW-8468270C]
Applied No NJ SHW07.05220 NPW GClMS, Exttact or Dir lnj, Capillary [SW-846 8270C]
Applied No NJ SHW07.0S230 NPW OClMS, Extract or Dir Inj, CapillBry [SW-846 8270C]
Applied No NJ SHW07.05240 NPW GClMS, Extract or Dir Inj, Capillary [SW-846 8270C]
Applied Nil NJ SHW07.05250 NPW OCJMS, Extlllct or Dir lqj, Capillary [SW-846827OC]
Applied No NJ SHW07.05260 NPW OClMS, Extract or Oir Ini, Capillary [SW-846 8270C]
Applied No NJ SHW07.05270 NPW OCIMS, Extl'llCt or Dir Inj, Capillary [SW-8468270C]
Applied No NJ SHW01.05280 NPW OCIMS, Extl'llct or Oir loj, Capillary [SW-S46 827OC]
Applied No NJ SHW07.05290 NPW GC/MS, Extlll\lt or Dir Inj, Capillary [SW-8468270C]
Applied No NJ SHW07.05300 NPW GClMS, Extract or Dir Inj, Capillary [SW-S46 8270C]
Applied No NJ SHW07.053l0 NPW GClMS, Extmct 01 Dir Ini, CapillBry [SW-846827OC]
Applied No NJ SHW07.05320 NPW GClMS, Extract or Dir Inj, Cspillary [SW-846827OC]
Applied No NJ SHW07.0S330 NPW GClMS, &ttact or Oir Ini, Capillary [SW-846 8270C]
KEY: A.E = Air and Emissions, BT = Biological Tissues, OW = Drinking Water, NPW = Non-Potable Water, SCM'" Solid ond Cbemicnl Materials
---Arumal Certified Parameters List -Effective as of 0710112009 until 06130/2010
Pllramlltcr Des\lriptlou
Nitroaniline (2-)
Nitroaniline (3-)
Nitroaniline (4-)
Chloronapbtbalene (2-)
Hexachlorobenzene
Hexachlorobutadiene (1,3-)
Hexachlorocyclopentadiene
Hexachloroethane
Hexachloropropene
Tricblorobenzene (1,2,4-)
Bis (2-cWoroethoxy) methane
Bis (2-cbloroethyl) ether
Bis (2-cliloroisopropyl) ether
Cblorophenyl-phenyl ether (4-)
Bromophenyl-phenyl ether (4-)
Dinitrotoluene (2,4-)
Dinitrotnluene (2,6-)
Isopborone
Nitrobenzene
Butyl benzyl phthalate
Bis (2-etby1hexyl) phthalate
Diethyl phthalate
Dimethyl phthalate
Di-n"blltyl phthalate
Di-n-octyl phthalate
Acenaphthene
Antluacene
AcenaphUlylene
Benzo(a)anthmcene
Benzo(a)pyreno
Benzo(b)fluorantbene
Benzo(ghl)perylene
Page 60f12
New Jersey Department of Environmental Protection
Natlonal Environmental Laboratory Accreditation Program
ANNUAL CERTIFIED P~TERLIST AND CURRENT STATUS
Effectlve 85 of 0710112009 until 0613012010
Laboratory Name: OUTREACH LABORATORY Laboratory Number: OKOOl Activity ID: NLC090001
311NASPEN ~ .,
BROKEN ARROW, OK 74012
Category: SHW07 -Organic Parameters, Clmlm8tograpby/MS
E6gibleto
Rcpol't
Status N~D8ta State Code Matrix Tedmlque Description Apprn'led Method Parametel' Descriptlon
Applied No Nl SHW07.0S340 NPW GCIMS, Eltt/'llct or Dir Inj, Capillary [SW-846 8270C) BBIlZO(k)fluornnthBne
Applied No NJ SHW07.0S3S0 NPW GClMS, Extract or Dir ll\i, Capillary (SW-846 8270C) Chrysene
Applied No NJ SHW07.0S360 NPW GC/MS, Exttact or Dir Inj, Capillary [SW-846 8270C) Dibenzo(a,h)antbmcene
Applied No NJ SHW07.05370 NPW Gc/MS, Extmct or Dir [nj, Capillary (SW-846 8270C) Fluoranthene
Applied No NJ SHW07.05380 NPW GClMS, Extmct or Dir [nj, CapiUalY [SW-846 8270C] Fluorene
Applied No NJ SHW07.05390 NPW GClMS, ExtJ1lct or Dir [nj, Capillary [SW-8468270C] [ndeno( l,2,3-i:d)pyrene
Applied No NJ SHW07.05410 NPW GeIMS, ExlJaCt or Dir Inj, Capillary [SW-846 827OC) Naphthalene
Applied No NJ SHW07.0S420 NPW GCIMS, ExlTact or Dir Inj, Capillary [SW-846 827OC) Phenanthrene
Applied No NJ SHW07.0S430 NPW GClMS, Extmct or Dir lnj, Capillary [SW-846 8270C] Pyrene
Applied No NJ SHW07.05440 NPW GC/MS, Extract or Dir [nj, Capillary [SW-846 8270C] Methyl phenol (4-chloro-3-)
Applied No NJ SHW07.05450 NPW GClMS, Extract or Dir Inj, Capilhuy [SW-846 &270C] Chlorophenol (2-)
Applied No NJ SHW07.05460 NPW GCIMS, Extract or Dir [nj, Capillary [SW -846 8270C] Dichloropbenol (2,4-)
Applied No NJ SHW07.05470 NPW GClMS, Extract or Dir )nj, Capillary [SW-8468270C] Dimethylphenol (2,4-)
Applied No NJ SHW07.05480 NPW GCIMS, Elttract or Dir Inj, Capillary [SW-B46827OC] Dinitrophenol (2,4-)
Applied No NI SHW07.05490 NPW GClMS, Elcttact or Dir )nj, Capillary [SW-846827OC) Dinitrophenol (2-metilyl-4,6-)
Certified Yes NJ SHW07.05500 NPW GC/MS, Extract or Dir Inj, Capillary [SW-846 8210C, Rev. 3, 12/96] Metbylphenol (2-)
Certified Yes NJ SHW07.0S510 NPW GC/MS, Extract or Dir lnj, Capillary [SW-846 827OC, Rev. 3,12196] Metbylphenol (4-)
Applied No NJ SHW07.05520 NPW GClMS, Extract or Oir Ioj, Capillary [SW-846 B270C] Nitrophenol (2-)
Applied No NJ SHW07.05530 NPW GClMS, ExtJ1lct or Dir lnj, Capillary [SW-846 8270C) Nitrophenol (4-)
Certified Yes NJ SHW07.05540 NPW GClMS, Extract or Dir Inj, Capillary [SW-846 8270C, Rev. 3, 12196] Pentachlorophenol
Applied No NJ SHW07.0SSS0 NPW GCIMS, Extract or Dir Inj, Capillary [SW-846 8270C] Phenol
Certified Yes Nl SHW07.05S60 NPW GC/MS, Extract or Dir [nj, Capillary (SW-846 8270C, Rev. 3, 12196] Trichlorophenol (2,4,5-)
Certified Yes NJ SHW07.05570 NPW GCIMS, Extract or Dir Inj, Capiliary (SW-846 8270C, Rev. 3, 12196] Trichloropbenol (2,4,6-)
Certified Yes NJ SHW07.05590 NPW GClMS. Extract or Dir Inj, Capillary [SW-846 827OC, Rev. 3, 12/96] MethyJpbenol (3-)
Applied No NJ SHW07.0S600 NPW GC/MS, Elttract or Dir Inj, Capfilaty [SW-846 8270C) Dibenzofuran
Applied No NJ SHW07.0S69I NPW GClMS, Extract or Dir Inj, Capillary [SW-846 827OC] Dichlorobenzene (1,2-)
Applied No NJ SHW07.0S692 NPW GClMS, Elttract or Die Inj, Capillary [SW-846 8270C] Dichlorobenzene (1,3-)
Applied No NJ SHW07.05700 NPW GC/MS, Extract or Dir Inj, Capillary [SW-8468270C] Dichlorobenzene (1,4-)
Applied No NJ SHW07.05710 NPW GClMS, ElctJ1lct or Dir Inj, Capillary [SW-846 8270C] Benzoic acid
Applied No NJ SHW07.0572S NPW GC/MS, Extl8ct or Vir I~, Capillary [SW-8468270D] Decane(n-)
Applied No NJ SHW07.0S730 NPW GClMS, ElctJ1lct or Dlr Inj, Capillary [SW-846 8270D] Octadecane (n-)
Applied No NJ SHW07.05745 NPW GCIMS, Eltbnct or Dir Inj, Capillary Petroleum Organics
KEY; AE = Air and Emissions, BT = Biological Tissues, DW = Drinking Water, NPW = NOll-Potable Water, SCM = Solid and Chemical Materials
--Annual Certified Pa/'lllueters List --Effective as of 07/01/2009 until 06130120 I 0 Page7ofl2
New Jersey Department of Environmental Protection
National Environmental Lab~ratory Accreditation Program
ANNUAL CERTIFIED PARAMETER-LIST AND CURRENT STATUS
Etlective as of 07/0112009 until 0613011010
Laboratory Name: OUTREACH LABORATORY Laboratory Number: OKOOl Activity ID: NLC090001
'31lN ASPEN
BROKEN ARROW, OK 74012
Category: SHW07 -Organic Parameters, ChromntograpllylMS
EliBiblc to
Report
Status NJData State Code Matrix Technique Description Approved Method
Certified Yes NJ SHW07.05750 NPW GClMS, Extrnct oe Dir Inj, CapiJbuy [SW-846 8270C, Rev. 3, 12/96]
Applied No NJ SHW07.05780 NPW GCIMS, Extrnct or Die Inj, Capillary [SW-8468270C]
Applied No N] SHW07.0S790 NPW GClMS, Extlllllt or Dir 11Ii, Capillal)' [SW-846 8210C]
Applied No NJ SHW07.05800 NPW GCJMS, Extmct or Die Inj, Capillary [SW-846827OC]
Applied No NJ SHW07.05810 NPW GCIMS, Extmct or Die Inj, Capillary [SW-8468270C]
Applied No NJ SHW07.05820 NPW GClMS, Extract or Die lnj, Capillary [SW-846 827Dq
Applied No NJ SJ-lW07.05830 NPW GCIMS, Extract or Dir lnj, Capillary [SW-846 8270C]
Applied No NJ SHW07.05840 NPW GC/MS, Extract or Oir loj, Capillary [SW-8468270C]
Applied No NJ SHW07.05850 NPW GClMS, &trnot or Dir Inj, Capillary [SW-846827OC]
Applied No Nl SHW07.05860 NPW GClMS, &tract or Die loj, Capillary [SW-8468270C]
Applied No NI SHW07.05870 NPW GCJMS, Extract or Oil" Inj, Capillary [SW-846 827OC]
Applied No N] SHW07.05880 NPW GClMS, Extract or Dir lnj, eapillary [SW-846 827OC]
Applied No NJ SHW07.05890 NPW GClMS, ExlIact or Oir Inj, Capillary [SW-8468270C]
Applied No NI SHW07.0S900 NPW GCIMS, Extract or Oir Inj, Capillary [SW-8468270C]
Applied No NJ SHW07 .0591 0 NPW GClMS, Extract or Dir Inj, Capillary [SW-846 8270C]
Applied No NJ SHW07.0S920 NPW GC/MS, Extract or Dir Inj, Capillary [SW-846 8270C]
Applied No NJ SHW07.0S930 NPW GClMS, Exlract or Dir lnj, Capillal)' [SW-846 8270C]
Applied No NI SHW07.0S940 NPW GClMS, Exlrnct or Dir Iqj, Capillary [SW-846 827OC)
Applied No NJ SHW07.0S9S0 NPW GCJMS, Exttact or Dir Inj, Capillary [SW-8468270C]
Applied No NJ SHW07.0S960 NPW ' GCJMS, Extract or Dir lnj, Capillary [SW-846827OC]
Applied No NI SHW07.05970 NPW GClMS, ExtIllCt or Dir Inj, Capillary [SW-846 8270C]
Applied No NJ SHW07.05980 NPW GC/MS, Extrnct or Dir Inj, Capillal)' [SW-846 8270C]
Category; WP.P09 -Radiodlem.: Radioactivity I RadionucJide
Eligible to
Report
Status NJData State Code Matrilt Technique Descri~tlon Approved Method
Certified Yes NJ WPP09.01000 NPW Proportional or Scintillation [EPA 900]
Certified Yes NJ WPP09.03000 NPW Proportional Counter [EPA 900)
Certified Yes NJ WPP09.03100 NPW Gamma Spectrometly [EPA 901.11
Certified Yes NJ WPP09.03200 NPW Gamma Spectrometry [EPA 901.11
KEY: AE = Air and Emissions, BT '" Biological Tissues, DW = Drinking Water, NPW = Non-Potable Water, SCM = Solid and Chemical Materials
--Annual Certified Paralllctem List -Effective as of 07/0112009 until 0613012010
Parameter Description
Pyridine
AlphaBHC
BetaBHC
DeIIaBHC
Lindane (ganuna BHC)
ChIoJdane (technical)
Chloroane (alpha)
Chloroane (gamma)
DOO(4,4'-)
DDE(4,4'-)
DDT (4,4'-)
Dieldrin
Endosulfan [
Endosulfan II
Eodosulfan sulfate
Endrin
&drin aldehyde
EDdrin ketone
Heptachlor
Heptacblor epoxide
Methoxychlor
Toxaphene
Parameter Description
Gross -alpha
Gross -beta
Cesium 134/137
Coba1t60
PageS orI2
New Jersey Department of Environmental Protection
National Environmental Laboratory Accreditation Program
ANNUAL CERTIFIED PARAMETER LIST AND CURRENT STATUS
Effective as of 07/0111009 uolil 06130/2010
Laboratory Name: OUTREACH LABORATORY Laboratory Number: OKOOI Activity ID: NLC090001
311N ASPEN
BROKEN ARROW, OK 74012
Category: WPP09 -Radiochem.: Radioactivity 1 Radionuclide
Eligible to
Report
Statu NJData State Code
Certified Yes NJ WPP09.03300
Certified Yes NJ WPP09.0S000
Certified Yes NJ WPP09.06000
Certified Yes NJ WPP09.06020
Certified Yes NJ WPP09.07000
Certified Yes NJ WPP09.08100
Certified Yes NJ WPP09.09000
Certified ND NJ WPP09.09010
CeJ1ified Yes NJ WPP09.l0000
Applied No NJ WPP09.11000
Category: WPPIO -Radon in Wastewater
Eligible to
Report
Status NJ Dam State Code
Certified Yf:> Nl WPPIO.OI000
Matrix
NPW
NPW
NPW
NPW
NPW
NPW
NPW
NPW
NPW
NPW
Matrix
NPW
Category: SHW02 -Cllaractcrlstics ofHllZlIrdous Waste
Eligible to
Report
Status NJData Stafe Code Matrix
Certified Yes NJ SHW02.010oo NPW,SCM
Certified Yes NJ SHW02.03OO0 NPW.SCM
Certified Yes NJ SHW02.06900 NPW,SCM
Certified Yes NJ SHW02.07000 NPW,SCM
Certified Yes NJ SHW02.08000 NPW,SCM
Teclmlqoe Description
Gamma Spectrometry
Precipitation
Radiochemical
Co-Precipitation I Beta Counting
Gamma Spectrometry
Precipitation I Beta Counting
Co-PrecipitatiDD I Alpha Counting
Isotopic Analysis I Alpha Spectrometry
DistillationlLiquid Scintillation
Radiochemical! Alpha Counting
Technique Description
liquid Scintillation
Technique Description
Pensky Martens
Aqueous Waste, Potentiometric
TCLP, Toxicity Procedure, ZHE
TCLP, Toxicity Procedure, Shaker
Synthetic PPT Leachate Procedure
Approved Method
[EPA 9OLl]
[SM 7500-Ra B)
[SM 750~Ra BI
[EPA 904.0]
[EPA90lJ]
[EPA 905.0]
[USER DEFINED ASTM 05174-91)
[ASTM D 3972-97]
[EPA 906.01
[EPA 907.0]
Approved Metllod
[USER DEFINED 8M 7500]
Approved Method
[SW-846 1010, Rev. 0, 9/86]
[SW-846 90408, Rev. 2, 1/95)
[SW-846 1311, Rev. 0,7/92]
[SW-8461311]
[SW-846 1312, Rev. 0,9/94]
KEY: AE'" Ail' and Emissions, BT = Biological Tissues, OW = Orinkillg Water, NPW = Non-Potable Water, SCM = Solid and Chemical Materials
-Annual Certified PammeteJS List --Effective as of 0710112009 until 0613012010
Parameter DcsuiptioR
Zinc 65
Radium -total
~dium-226
Radium-228
Photon Emitters
Strontium -90
Uranium
Uranium
Tritium
Plutonium
Parameter Description
Radon
Parameter Description
Ignitability
Corrosivity -pH waste, >20% water
Volatile oJg&R!cs
Metals
Metals -organics
Page90f12
New Jersey Department of Environmental Protection
National Environmental Laboratory Accreditation Program
ANNUAL CERTIFIED PARAMETER LIST AND CURRENT STATUS
Effective as of O71U1I2009 aRill 0613012010
Laboratory Name: OUTREACH LABORATORY Laboratory Number: OKOOI Activity 10: NLC090001
311N ASPEN
BROKEN ARROW, OK 74012
Category: SHW04 -Inorganic Parameters
Ellgiblcto
Report
Status NJ Data State Code Matrix Technique Description Approved Method Parameter DClicrlEtloR
Certified Yes NJ SHW04.0S000 NPW, SCM lCP [SW-846 601OB, Rev. 2,12196] Aluminum
Certified Yes NJ SHW04.06500 NPW,SCM ICP [SW-846 6010B, Rev. 2, 12/96] Antimony
Certified Yes NJ SHW04.09000 NPW,SCM lCP [SW-846 60 lOB, Rev. 212196] Arsenic
Certified Yes NJ SHW04.11500 NPW,SCM ICP [SW-846 60 lOB, Rev. 212196] Barium
Certified Yes NJ SHW04.13500 NPW,SCM lCP [SW-846 60 lOB, Rev. 2 12196] Beryllium
Certified Yes NJ SHW04.15100 NPW,SCM ICP [SW-846 6010B, Rev. 2, 12/96] Boron
Certified Yes NJ SHW04.15500 NPW,SCM lCP [SW-846 60108, Rev. 2 12/96J Cadmium
Certified Yes NJ SHW04.17500 NPW,SCM ICP [SW-846 6010B, Rev. 2 12/96] Calcium
Certified Yes NJ SHW04.l8S00 NPW,SCM lCP [SW-846 6010B, Rev. 2.12/96] Chromium
Certified Yes NJ SHW04.22500 NPW,SCM ICP [SW-846 6010B, Rev. 2 12196] Cobalt
Certified Yes NJ SHW04.24S00 NPW,SCM ICP [SW-846 601OB, Rev. 2 12196] Copper
Certified Yes NJ SHW04.26000 NPW,SCM ICP [SW-846 6010B, Rev. 2 12196] Iron
Certified Yes NJ SHW04.27S00 NPW,SCM ICP [SW-846 6010B, Rev. 212196] Lead
Certified. Yes Nl SHW04.30500 NPW,SCM )CP [SW-846 60108, Rev. 2,12/961 Magnesium
Certified Yes NI SHW04.31500 NPW,SCM lCP [SW-846 60108, Rev. 2,12/96] Manganese
Certified Yes NJ SHW04.33000 NPW,SCM AA, Manual Cold Vapor ISW-846 7470A, R6V. 1,9194] Mercury -liquid waste
Certified Yes NI SHW04.34000 NPW,SCM ICP [SW-846 601OB, Rev. 2 12196] Molybdenum
Certified Yes NJ SHW04.3SS00 NPW,SCM ICP [SW-846 60108, Rev. 2, 12/96J Nickel
Certified. Yes NJ SHW04.38000 NPW,SCM ICP [SW-846 60 lOB, Rev. 212/96] Potassium
Certified Yes NI SHW04.39000 NPW,SCM ICP [SW-846 6010B, Rev. 2 12196] Selenium
Certified Yes NI SHW04.41000 NPW,SCM ICP [SW-846 6010B, Rev. 2 12196] Silver
Certified Yes NJ SHW04.43000 NPW,SCM lCP [SW-846 6010B, Rev. 2 12/96J Sodium
Certified Yes NJ SHW04.4400Q NPW,SCM lCP [SW-846 6010B, Rev. 2 12/96J Strontium
Certified Yes NJ SHW04.45000 NPW,SCM ICP [SW-R46 60108, Rev. 212196] Tballium
Certified Yes NJ SHW04.47500 NPW,SCM rcp [SW-846 60108, Rev. 212196] Vanadium
Cllrtified Yes NJ SHW04.49000 NPW,SCM ICP [SW-846 6010B, Rev. 212196] Zinc
KEY: AS = Air and EmissioDs, BT"" Biological Tissues, OW = Drinking Water, NPW = Non-Potable Water, SCM = Solid und Chemical Materials
-Annual Certilied Pommeters List --Efl"ective as of 07/0112009 until 0613012010 Page IOof12
New Jersey Deparir!lent ofEnvh-onmental Protection
National Environmental Laboratory Accreditation Program
ANNUAL CERTIFIED PARAMETER LIST AND CURRENT STATUS
EffettiveBs of 0710112009, uatll 06/301l010
Laboratory Name: OUTREACH LABORATORY Laboratory Number: OKOOI Activity ID: NLC090001
311NASPEN '
BROKEN ARROW, OK 74012
Category: SHW09 -MIscellaneous Parameters
Eligible to
Report
StatUI NJDnta State Code
Applied No NJ SHW09.02000
Applied No NJ SHW09.04100
Certified Yes NJ SHW09.10000
Category: SHW04 -Inorgunie Parameters
Eligible to
Stain
Certified
Certified
Certified
Report
NJ Data State Code
Yes
Yes
Yes
NJ
NJ
NJ
SHW04.03000
SHW04.21000
SHW04.33500
Matrix
NPW,SCM
NPW,SCM
NPW,SCM
Matrix
SCM
SCM
SCM
Category: SHWOS -OJllanlc Parameters, Prep. J Sereening
Eligible to
Report
Status NJ Data State Code Matris
Certified Yes
Certified Yes
NJ
NJ
SHWOS.l2000
SHW05.l7000
Category: SHW09 -Misc:cllaneous Parameten
Eligiblcto
Report
Status NJData State Code
Certified Yes NJ SHW99·60000
Certified Yes NJ SHW09.60IOS
Certified Yes NJ SHW09.60106
Certified Yes NJ SHW09.60110
Certified Yes NJ SHW09.60120
Certified Yes NJ SHW09.60130
Certified Yes NJ SHW09.60140
Certified Yes NJ SHW09.60150
SCM
SCM
Matrix
SCM
SCM
SCM
SCM
SCM
SCM
SCM
SCM
Technique Dl!!ltription
Distillation
TibimetriclManual Spectropbotomebic
Water Extrdction, Distillation
Teclmigue Deseription
Acid Digestion, Soil Sediment & Sludge
Colorimetric
AA, Manual Cold Vapor
Technique Description
Cleanup-Florlsil
Cleanup-Sulfuric AcidlKMn04
Technique Description
Proportional Counter
Radon Emanation
Precipitation
Precipitation
Gamma Spectrometry
Gamma Spectrometry
Gamma Spectrometry
Gamma Spectrometry
Approved MetJIod
[SW-346 9010B, Rev. 2, 12196]
[SW-846 9014, Rev. 0, 12J96)
[SW-8469031]
Approved Method
(SW-846 3050B, Rev. 2, 12196]
[SW-846 7196A, Rev. 1,7192)
[SW-846 7471 A, Rev. 1,9194)
Approved Method
[8W-846 3620B, Rev. 2, 12196]
[SW-846 3665A, Rev. 1, 12/96]
Approved Method
[SW-lI46 9310, Rev. 0, 9186)
[DOERa-04]
[8M 7500-Ra B]
[SW-846 9320, Rev. 0,9/86]
[DOE 4.5.2.3]
[DOE 4.5.2.3]
[DOE 4.5.2.3]
[DOE 4.5.2.3]
KEY; AE = Air and Emissiolls, BT 0= Biological Tissues, DW'" Drinking Water, NPW = Non-Potable WatlD', SCM = Solid and Chemical Materials
-Annual Certified Parameters List -Effective as of 07101/2009 until 06/3012010
Parameter Description
Cyanide
Cyanide
Sulfides -extlllctable
Parameter Description
Metals
Chromium (VI)
Merowy -solid waste
Parameter De$cription
Semivolatile organics
Semivolatile organics
Parameter Description
Gross -alpha-beta
Radium -226
RadiUln -226
Radium -228
Cesium 134/137
Cobalt 60
Zinc 65
Barium 133
Pace II ofl2
New Jersey Department of Envnronmental Protection
National Environmental Laboratory Accreditation Program
ANNUAL CERTIFIED PARAMETER LIST AND CURRENT STATUS
Effectlvo as ~r 07/0112009 until 0613012010
Laboratory Name: OUTREACH LABORATORY Laboratory Number: OKOOl Activity ID: NLC090001
311NASPEN
BROKEN ARROW, OK 74012
Category! SHW09 -Misecllaneaus Pllrameters
Eligible to
Report
Status NJDllta State Code Matrix Teclmigue Description Approved Method
CertifHld Yes NJ SHW09.60200 SCM Precipitation 1 Bela C<luntiog [DOESr-OI, Sr-02]
Certified Yes NJ SHW09.60300 SCM Fluorometry [ASTM D 5174]
Certified Yes NJ SHW09.60310 SCM Alpha Spectrometry [DOEU-02]
Certified Yes NJ SHW09.60400 SCM Alpha Spectrometry [DOE 4.5.5]
KEY: AE = Air Dnd Emissions, BT = Biological Tissues, DW '" Drinking Water, NPW = Non-Potable Water, SCM = Solid and Chemical Materials
-Annual Certified Parameters List -Effective as of 07/0112009 until 06130120 I 0
Parameter Description
Strontium -89, 90
Uranium
Uranium
Thorium
Pnge 12 of)2
OKLAHOMA
DEPARTMENT OF ENVIRONMENTAL QUAUTr
•. .for 0 dOOll, oltmdive, Plasp8TtJUS OklohDmo
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
State Laboratory ID: 9517; D9923
EPA ill: OK00922
Certificate #: 2009-105
·Outreach Laboratory
311 North Aspen
Broken Arrow, OK 74012
has been certified for the examination of environmental samples for fields of testing listed on the laboratory's Scope of Accreditation.
Continued certification is contingent upon successful on-going compliance with OAC 252:301 which was promulgated
Bnd adopted pursuant to the Oklahoma Environmental Quality Code (Code), 27AO.S. § 2-4-101 et seq.
Specific methods and analytes certified are cited on the laboratory's Scope of Accreditation.
The Scope of Accreditation and reports of on-site inspections are on file at the Oklahoma DEQ, Customer Services Division,
Laboratory Accreditation Program, 707 N Robinson, P.O. Box 1677, Oklahoma City, Oklahoma 73101-1677,
[phone], www.deq.state.ok.us.Clients and customers may verify with this agency the
laboratory's certification status for particular methods and analytes.
ISSUED: 9/1/2009 EXPffiES: 8131/2010
~ G~/r~
uncan, Customer Services Division Director David Caldwell, Laboratory Accreditation Program
This certificate Is valid proof of certilicatlon only when associated with its Scope of Accreditation.
OKlAHOMA
DEPARTMENT Of ENVIRONMENTAl QUAlITY
., • for 0 deon, otlllJclive. prosperous Oklahoma
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
Broken Arrow. OK 74012
(918)-251-2515
""'1."\EJ~~ .~ -;', .....• '~"'L"" ~", k '. ,' • .. '~II 1#" ~~~'f.. ~: .. ~~ .. "
" ~ '. , ..... ~ ... ®:
,t ., •. ~ '"" .• 4) _ .... " ~
. ~'.~
Laboratory 10: OK00922
State lab 10: 9517
Safe Drinking Water Program
Certificate Number: 2009-105
Date ofIssue: 91112009
Expiration Date: 8/31/2010
Has demonstrated the capability to analyze environmental samples in accordance with Oklahoma Rules 252:301
and is hereby granted CERTIFICATION FOR:
BariUm 133 EPA 1101.1 OW Suspended
Cesiurn-134 EPA 901.1 OW Good Standing
Ceslum-137 EPA 1101.1 OW Good Standing
Cobalt 60 EPA9D1.1 OW Good Standing
Gross alpha-beta EPA 1100 OW Good Slanding
Gross gamma EPA 901.1 OW Good Standing
Lead·210 EPA 901.1 OW Good Standing
Manganese-54 EPA 901.1 OW Good Standing
Radioactive iodine (iodine-131) EPA 901.1 OW Good Standing
Radiurn·226 X SM 161191hEO 750D-Ra B OW GoOd Standing
Radium-22e EPA 904 OW Good Standing
Strontium·eg. SO EPA 905 OW Good S1andlng
Strontium·gO EPA 905 OW Suspended
Tritium EPA 906 OW Good Standing
Uranium ASTM 05174·97 OW GoOd Standing
Zino65 EPA 901.1 OW GoOd Standing
ow .. Drinking Water; NPW" Non-Potable Water: S = Solids
This analyte list supercedes aU previously issued.
DISPLAY IN A PROMINENT POSITION Certification Officer
Page 1
OKLAHOMA
DEPARTMENT OF ENVIRONMENTAt QUAlITY
•.• for 0 cleon, ottroctive, PTOSPS/OUS Oklnhomo
Laboratory 10: OK00922
State Lab 1D: 9517
Clean Water ProQram
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
Broken Arrow, OK 74012
(918)-251-2515
Certificate Number: 2009-105
Date of Issue: 91112009
Expiration Date: 8131/2010
Has demonstrated the capability to analyze environmental samples in accordance with Oklahoma Rules 252:301
and is hereby granted CERTIFICATION FOR:
1,1,1,2-Tetrachloroethane
1.1.1,2-Tetrachloroethane
1.1,1,2-Tetr8chloroelhane
1,1,1-Trtchloro-2-propanone
1,1,1-Trfchloro-2-propanone
1,1,1-Trichloroethane
1,1,1-Trfchloroethane
1.1,1-TrlChloroe!hane
1.1 .2.2-Tetrachloroethane
1,1,2.2-Tetrachloroethane
1,1.2,2-Telrachloroe!hane
1,1.2-TrlChloro·1 ,2,2·trifluoroethane
1,1.2· Trichloro-1.2,2·tlffiuoroethBne
1.1.2·Trfchloroethane
1,1.2·Trfchloroethane
1,1,2-Trfchloroethane
1,1.0ichloroethane
1,1·Oichloroethane
1,1-0ichloroethane
1,1-Dichloroethylene
1,1-Dlchloroethylene
1.1·0Ichloroethylene
1,1-Dichloropropene
1.1-Dichloropropene
1.2.3.4-0Iepoxybutane
1.2,3,4-Diepoxybutane
1.2,3.4-Tetrachlorobenzene
1.2.3,4-Tetrachlorobeilz.ene
1,2,3-Trlchlorobenzene
1,2,3-Trtchlorobenzene
1.2,3-Trtchlorobenzene
1,2.3-Trfchloroprapane
1.2.3-Trfchloroprapane
1.2.4.5-Tetrachlorobenzene
l,2,4,5·Tetrachlorobenzene
1,2,4,5-Tetrachlorobenzene
1.2,4·Trlchlorobenzene
1.2.4-Trichlorobenzena
1.2,4-Trlchlorobenzene
l,2,4-Tllchlorobenzene
1,2.4-Trfchlorobenzene
1.2,4-Tilchiorobenzena
1,2.4-TrlchlolObenzene
1.2.4-Trichlorobenzene
1.2.4-Trlmethylbenzene
EPA 624
EPA 82606_2_1996
EPA 82608_2_1996
EPA 82606_2_11196
EPA 82606_2..1998
EPA 624
EPA 82606_2_1996
EPA 82608_2_1996
EPA 624
EPA 8260B_2_1996
EPA 82608_2_1996
EPA 8260B~_1996
EPA 82608_2_1996
EPA &24
EPA 82608_2_1996
EPA 82606_2_1996
EPA 624
EPA 82608_2_1996
EPA 8260B_2_1996
EPA 624
EPA 8260B_2_1996
EPA 8260B_2_1996
EPA 82608_2_1996
EPA 82806_2.-1998
EPA 82606_2_1996
EPA 82606_2_1996
EPA 8260B_2_1996
EPA 82608_2_1996
EPA 624
EPA 82606_2_19915
EPA 82606_2_1996
EPA 8260B_2_1996
EPA 82608_2_1996
EPA 8270B_(9/94)
EPA 8270B_(9/94)
EPA 8270C_3_1996
EPA 624
EPA 625
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82708_(9194)
EPA 82708_(9/94)
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 82608_2_1996
Page 1
NPW
S
NPW
NPW
S
NPW
S
NPW
NPW
NPW
S
NPW
S
NPW
S
NPW
NPW
S
NPW
NPW
NPW
S
S
NPW
NPW
S
S
NPW
NPW
S
NPW
S
NPW
NPW
S
NPW
NPW
NPW
S
NPW
S
NPW
S
NPW
NPW
Goot! Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good St8nt1ing
Good Stantling
Good Stentling
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
GQod standing
GQod standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standln!l
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good StBnding
Good Standing
Good Standing
Good Stantllng
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Oklahoma Department of Environmeotal Quality
Laboratory Accreditation Program
OKLAHOMA
DEPARTMENI OF ENVIROt4MENTAl QUAlliY
•. .for a clean, OIIracJive, pl0SperouS OklIJhoma
LaborcltOry 10; OKOO922
State Lab 1D; 9517
Clean Water Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
Broken Arrow, OK 74012
(918)-251-2515
Certificate Number: 2009-105
Date of Issue: 9/112009
Expiration Date; 8/31/2010
Has demonstrated the alpability to analyze environmental samples in accordance with Oklahoma Rules 252:301
and Is hereby granted CERTIFICATION FOR:
1,2,4-Trimethylbenzene
1,2-Dibrormr3-<:hloropropllne (Deep)
l,2-Dibromo-S-chloropropane (Deep)
1,2-DibrOl1lC)-3.(:hloropropane (DBep)
1,2-Dibromo-3-ehloropropane (Deep)
1,2-Dibromo-3-chloropropane (Deep)
1,2-Dibroma-3-ehloropropane (Deep)
l,2-Dibromoelhane (EDB, Elhyl8ne dibromide)
1,2-Dibrom08lh8ne (EDB. Ethylene dibromide)
l,2-Dibromoethane (EC8. Ethylene dibromide)
i .2-Dichloroller1:zeI18
1,2-Dichloroben%ene
1,2·Didllorobenzene
1.2-Dichlorobenzene
l,2-Dichlorobenzene
1.2-Dichlorobenzene
1.2-Oichlorobenzene
l,2-Dichlorobenzene
1,2-Dichloroethane
1,2-Dichloroethane
l,2-Dlchloroethane
1,2-Dichloropropane
1,2-Dichloropropane
l,2·Dichloropropane
1,2-Dinitroben:i:ene
1,2-Dinltrobenzene
1,2-Dinltrobenzene
1,2-DlniIrobenzene
1,2-Dlphenyihydrazine
1,2-Diphenylhydrazine
1,2-Diphenylhydrazine
1,2-Oiphenylhydrazine
1,2-Diphenylhydrazine
1,3,5·Trimethytben~ne
1,3,5-Trimelhylbenzene
1,3,5-Trinilrobenzene (1,3,5-TNB)
1.3,5-Trfnitrobenzene (1,3,5-TNB)
l,3-Dichloro-2·propanol
1,3-Dichloro-2-propanol
1,3-Dichlotobenzene
1,S-Dichlorobenzene
1,3-Diclllorobenzene
1,S-Oiclllorobenzene
1,3-Dichlorobenzene
1,3-Dichlorobenzene
EPA 82608_2_1996
EPA 62608_2_1996
EPA 62608_2_1996
EPA 62708_(9/94)
EPA 82708_(9194)
EPA 6270C_3_1996
EPA 8270C_3_199S
EPA 624
EPA 8260B_2_1996
EPA 82608_2_1996
EPA 624
EPA 625
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82708_(9/94)
EPA 82708_(9/94)
EPA 8270C_3_19S6
EPA 8270C_3_1996
EPA 624
EPA 82608_2_1996
EPA 82608_2_1996
EPA 624
EPA 82608_2_1996
EPA 8260B_2_1996
EPA 82708_(9/94)
EPA 82708_(9194)
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 625
EPA 82709_(9/94)
EPA 8270B_(9/94)
EPA 8270C_3_199fl
EPA 8270C_:U996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 8270C_3_199S
EPA 8270C_3_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 624
EPA 625
EPA 62608_2_1996
EPA 826DB_2_1996
EPA 82708_(9194)
EPA 82706_(9/94)
Page 2
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Good Standing
Good Standing
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Good Standing
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Good Standing
Good Standing
Good Standing
Good Standing
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Good Standing
Good Standing
Good Stllnding
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Gcod Standing
Good Standing
Good Standing
Good StandIng
Good StandIng
Good Standing
Good Standing
Good Stending
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
OKLA.HOMA
DEPARTMENT Of ENVIRONMENTAL QUALITY
••. IDr 0 deon, oltroclive, prosperous OkJohomo
Laboratory ID: OK00922
State latJ ID: 9517
Clean Water Program
Oklahom~ Department of Environmental Quality
Laboratory Accreditation Program
Scope of Accreditation
Outreach Laboratory
~11 North Aspen
Broken Arrow, OK 74012
(918)-251·2515
Certificate Number: 2009-105
Date of Issue: 9/1/2009
expiration Date: 813112010
Has demonstrated the capability to analyze environmental samples In accordance with Oklahoma Rules 252:301
and is hereby granted CERTIFICATION FOR:
1,3·Dict1lorobenzene
1,3-Diehlorobenzeoe
1,3·Dicllloropropane
1,3.Dicllloropropane
1,3·DinHrobenzene (1,3-DNB)
1,3·Dinltrobenzene (1,3-0NB)
1,3-Dlnitrobenzene (1,3-DN8)
1 ,3-Dinilrobenzene (1,3-0NB)
1,4·DlchIorobenzene
1,4-Dichlorobenzene
1,4·Dichlorobenzene
1,4·0lchlorobenzene
1.4·Dlchlorobenzene
1.4-Dlchlorobenzene
1.4·0IchJorobenzene
1,4·Dlchlorobenzene
1,4-Dinltrobenll:ene
1,4-Dinitrobenzene
1,4-Olnitrobenzene
1,4·DinitJobenzene
1 A·Dioxane (1,4-Diethyleneoxide)
1.4·Dioxane (1,4-Diethyleneoxide)
1,4·Naphthoquinone
1,4·Naphthoquinone
1,4-Naphthoquinone
1,+Naphthoquinone
1 ,4·Naphthoquinone
1.4·Phenylilnedlamine
1,4·PIlenylenediamine
1,4·Phenylenediamine
1,4-PIlenylenedlamlne
1·AcelyI-2-thlourea
1·AcelyI-2·thlourea
1·Acetyl-2·thlourea
1·Acetyl-2-1hIOLlfea
1·Chloronaphlhalene
1.Chloronaphthalene
1·Chloronaphll'lalene
1·Chloronaphthalene
1·Chloronaphthalene
1.Napl1thylamlne
1.NaphthyJamine
1·Naphthylamine
1·Naphthylamine
1·Naphthylamlne
EPA 8270C_3_1998
EPA 11270C_3_1998
EPA 82608_2_1996
EPA 8260B..2_1996
EPA 8270B_(,1/94)
EPA 82708_(9/94)
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 624
EPA 625
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82708_(9194)
EPA 8270B_(9/94)
EPA 6270C_3_1996
EPA 8270C_3_1996
EM 62708_(9/94)
EPA 82708_(9/94)
EPA 8270C_3_1996
EPA 8270C_3_1998
EPA 82806_2_1998
EPA 82608_2_1998
EPA 625
EPA 82706-'9194)
EPA 8270B_(9/94)
EPA 827OC_3_1996
EPA 6270C_3_1998
EPA 82706_(9194)
EPA 82708_(9194)
EPA 8270C_3_1998
EPA 827OC_3_1998
EPA 82708_(9194)
EPA 8270B_(9/94)
EPA 827OC_3_1998
EPA 8270C_3_1996
EPA 825
EPA 82708_(9/94)
EPA 82708_(9194)
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 825
EPA 82706_(9/94)
EPA 8270B_(9/94)
EPA 8270C_3_1996
EPA 8270C_3_1996
Page 3
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Good Standing
Good Standing
Good Standing
Good Standing
Good Stanliing
Goo(j Stamling
Good Standing
Good StanCling
Good StaOlling
Good Standing
Good StllOl1ing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Stending
Good Standing
.Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Stano:ling
Good Standing
Goo\! Standing
Good Slandlng
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
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~~"'·IU.~ .... ~. 'Sto ·_"'"
OKlAHOMA
DEPARTMENT Of ENVIRONMENTAl QUAlIlY
•• .for 0 clean, ortrocfive, prO$perous OklohomtJ
Laboratory ID: OK00922
State Lab 10: 9517
Clean Water Program
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
Broken Arrow, OK 14012
(918)-251-2515
Certificate Number. 2009-105
Date of Issue: 91112009
expiration Date: 8131/2010
Has demonstrated the capability to analyze environmental samples In accordance with Oklahoma Rules 252:301
and Is hereby granted CERTIFICATION FOR:
1-propanol
1·propancl
2,2-Dichloropropane
2.2-01chloropropane
2.2-oxybls (1-chloropropane)
2,3,4,60 Tetrachlorophenol
2,3.4,60 Tetracl1lorophenot
2,3,4.6-Tetracl1l0r0p1!eno1
2,3.4,e-Tetrachlorophenot
2.3,5-Trichlorophenol
2,3,5-Trlchlorophenol
2,3,5-Trlchlorophenol
2.3.6-Trlchlorophenol
2,3,6-Tr1chIorophlinol (4C)
2,4.5· TrichlorophenoJ
2.4.5·Trlchlorophenol
2,4.S·Trlchlorophenol
2,4,5·Trlchlorophenol
2.4,S·Trlchlorophenol
2,4.5-Trlmethylaniline
2,4,5-Tllmethylaniline
2,4,6-Trlchlorophenol
2.4,e-Trlchlorophenol
2,4,S.Trlchlorophenol
2,4,6-Trlchlorophenol
2,4,5-Trichlorophenol
2.4-0
2.4-0
2,4-Diamlnotoluene
2,4-Dlamlnotoluene
2,4-01llmlnotoluene
2,4·0lamlnotoluene
2,4-0ichlorophenol
2,4·Dichloropl1encl
2.4-Diehlorophenol
2.4·Dichlorophenol
2,4-Dldllorophenol
2.4-Dimethylpl1enol
2.4.Dlmethylphenol
2.4-Dimethylphenol
2,4-Dirnethylphenol
2.4·Dimethylphenol
2,4·Dinitropllenol
2,4·Dinilrophenol
2,4-0initrophenol
EPA 62608_2_1996
EPA 6260B_2_199tl
EPA 112008_2_1996
EPA 82608_2_1996
EPA 625
EPA 82708_(9194)
EPA 82708_(9/94)
EPA 827OC_3_'996
EPA 827OC_3_19&6
EPA 625
EPA 827OC_3_1996
EPA 827QC_3_199B
EPA 625
EPA 625
EPA 625
EPA 82708_(9/94)
EPA 62708_(9194)
EPA 8270C_3_1996
EPA 827OC_3_1996
EPA 8270C_3_1996
EPA 827OC_3_1996
EPA 625
EPA 82708_(9194)
EPA 82108_(9194)
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 6151A_(1/96)
EPA 8151A_(1198)
EPA 62708_(9/94)
EPA 82708_(9/94)
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 625
EPA 82708_(9194)
EPA 82708_(9/94)
EPA 8270C_3_'99S
EPA 11270C_3_'996
EPA 625
EPA 82708_(9194)
EPA 82708_(9/94)
EPA 827OC_3_1996
EPA 8270C_3_'996
EPA 625
EPA 62708_(9/94)
EPA 62708_(9/94)
Page 4
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Good Standing
Good Standing
Good Slanding
Good Slandlng
Good standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Slanding
Good Standing
Good Standing
Good Standing
Good Standing
Goed S1anding
Good Slanding
Good Standing
Good Slandlng
Good Slanding
Good Standing
Good Standing
Good Slanding
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Slanding
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Slanamg
Good Standing
Good Standing
Good Standing
Good Standing
Good StallCfrng
Good Standing
Good Standing
Good stanCiing
OKLAHOMA
DEPARTMENT Of ENVIRONMENTAl QUAlITY
.• .for 0 clean, otrracJiVf, pfDS(JefOUS OklDhoma
Laboratory 10: 01<00922
State Lab 10: 9517
Clean Water Program
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
Broken Arrow, OK 74012
(918)-251-2515
Certificate Number: 2009-105
Date of Issue: 9/1/2009
expiration Date: 8/3112010
Has demonstrated the capability to analyze envIronmental samples In accordance with Oklahoma Rules 252:301
and is hereby granted CERTIFICATION FOR:
2.4.Dinilrophenol
2.4·Dinltrophenol
2.4·Dlnltrotol~e (2,4·0NT)
2.4-Dlnltrotoluene (2.4·DNT)
2.4-Dlnltrotoluene (2,4.0NT)
2.4·Dimll'otoluene (2,4.0NT)
2.4·Dlnltrotoluene (2,4-0NT)
2.5-Dichloropllenol
2.6·Dichforophenol
2,6-Dich1QrQPllenol
2.6-OIchlQrophenol
2.6-D1nltrQtokJene (2,II-DHT)
2,6-OinitrQloJuene (2,6·0NT)
2,6.Dlnitrotoluene (2,6-0NT)
2,6·Dinitrotoluene (2,B·ONT)
2,e·Dlnltrotoluene (2,8·0NT)
2-Acetylamlnoftuorene
2-Acetyiamlnonuorene
2·Acelylamlnofluorene
2-Ac:elylamlnonuorene
2-Amlnoanthraquinone
2-Amlnoanlhraqulnone
2·Aminoanthraquinone
2·Aminoanlhraquinone
2·Bulanona (Methyl ethyl ketone. MEl<)
2-Bulanone (Melhyl ethyl ketone, MEl<)
2-Bulanone (Methyl ethyl ketone, MEK)
2·Chloro-1,3·butadiene (Chloroprene)
2-Chloroelhanol
2-ChloroethanOi
2-Chloroethyl vinyl ether
2-Chloroeth~1 vln)o1 ether
2-Chloroethyl vinyl elher
2·Chloronapllthalene
2-Chloronapllthalene
2-Chloronaphthalene
2-Chloronaphthalene
2-Chlcronapllthalene
2-ChlorQphenol
2-Chlorophenol
2-ChlorQpllenoi
2-Chloropllenol
2-Chlorophenol
2·Chlorotoluene
2-Chlorotoluene
EPA 8270C 3 1996
EPA 8270C:3: 19~6
EPA62~
EPA 82706_(9/94)
EPA 82708_(9/94)
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 82708_(9/114)
EPA 8270B_{9/94)
EPA 8270C_3_1998
EPA 8270C_3_1996
EPA 625
EPA 8270B_(9194)
EPA 8270B_(9/94)
EPA 82700_3_1998
EPA 827OC_3_1996
EPA 82708_{9(94)
EPA 82708_(9/94)
EPA 8270C_3_1996
EPA 827OC_3_19116
EPA 82708_(9/94)
EPA 82708_(9/94)
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 1124
EPA 82608_2_1998
EPA6260B 2 1998
EPAe24 --
EPA 82608 2 19116
EPA 8260B:( 1996
EPA 624
EPA 8260B_2_1996
EPA 82608_2_11196
EPA 625
EPA 6270B_(9194)
EPA 8270B_(9/94)
EPA 8270C_3_199S
EPA 6270C_3_1996
EPA 625
EPA 82708_(9/94)
EPA 82708_(9194)
EPA 8270C_3_1996
EPA 8270C_3_1998
EPA 82608_2_1998
EPA 82608_2_1996
PageS
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G(lQtI Slanding
Good standing
Good SIending
Good Standing
Gocxl Standing
Good Slanding
Good Standing
Good standIng
Good Standing
Good Standing
GQOd Standing
GQOd Standing
Good standing
Goot! standIng
Good Standing
Good Standing
Good standing
Goocl standing
Gocxl standing
Good Standing
Good Slanding
Good Standing
Good standing
Gocxl Standing
Good standIng
Good Standing
Good standing
Good Slending
Good standing
Good Standing
Good Standing
Good Slending
Good Standing
Good standing
Good Standing
Good Standing
Good Slanaing
Good standing
Good Standing
Good Slandlng
Good Standing
Good Standing
Good Standing
Good standing
Good SIending
OKlAHOMA
DEPARTMENT Of ENVIRONMENIAl OUAUIY
..• fIlr a clerm, 01l70ctivB, pr05peTDUS Oklahoma
Laboratory ID: OK00922
State lab ID: 9517
Clean Water Program
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
Broken Arrow, OK 74012
(916)-251-2515
Certificate Number: 2009-105
Date of Issue: 911/2009
expiration Date: 8/3112010
Has demonstrated the capability to analyze environmental samples in accordance with Oklahoma Rules 252:301
and is hereby granted CERTIFICATION FOR:
2.CydQhexyl .... 6-dinilrophenol
2·CycIOhexyl-4.641nllropheno/
2.CyclohexyJ"',6-dlnllrophenol
2·CyclohexyJ-4,Il-dJnllrophunol
2·Hexanone
2-Hexanone
2·Hydroxypropionilrlle
2-HydroxypropionHrfIe
2-MeIhyI-4.8-d1nilTophenol
2-MeIhyl"',ll-dlnltrophenol
2-Mefhylnaphthalene
2-Methylnaphlhalene
2-MefhylnaphthaJene
2-Melhylnaphlhalene
2-MelhylphenOl (o-Cr.,ol)
2-Melhylpheno1 (o-cr"o1)
2-Methylphenol (o-Creaol)
2·Methylphenol Co-Cresol)
2-Naphlhylemlne
2.Naphlhyiamine
2.Nephlhylamlne
2-Naphlhylamine
2-Naptllhylamlne
2-N~roanlllne
2·Nltroanillne
2-Nltroanlline
2-NilroaniUne
2-Nitrophenol
2-Nnrophenol
2-Nltrophenol
2-Nnrophenol
2-Nltropheno1
2-Nltropropane
2-Nltropropane
2-Pentanona
2-Pentanone
2-Plcoline (2-Me\hylpyrldine)
2-PicoTine (2·Methylpytidine)
2-PicoHne (2-MelhyJpyridine)
2-Plcofine (2·Melhylpyridlne)
2-PlcoUne (2·MelhyIpyridlne)
2·Plcollne (2·Methylpyrldine)
2-Plcoline (2·Meltlylpyridine)
2·Propanol
2.Propancl
EPA 112708_(9/94)
EPA 62706_(9/94)
EPA 8270C_3_'996
EPA 8270C_3_19ie
EPA 82808_2_1996
EPA 82808_2_'996
EPA 82608_2_1996
EPA 8260B_2_19i6
EPA 8270C_3_1996
EPA8210C 3 1996
EPA 82109:::(9i94)
EPA 8270B_(9194}
EPA 8270C 3 1996
EPA 8270C:(1996
EPA 6210B_(9194}
EPA 821Q8_(9194}
EPA 8270C_3_'996
EPA 8210C_3_1996
EPA 625
EPA 82708_(9194)
EPA 82708_(9/94)
EPA 8270C :3 1996
EPA 8210C:( 1996
EPA 8270B_(9/94)
EPA 8210B_(9/94)
EPA 8270C_3_1996
EPAB270C_:3_1996
EPA 625
EPA 82708_(9194)
EPA 8270B_(9194}
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8260B_2_1996
EPA 82608_2_1996
EPA8260B 2 1996
EPA 626OB:2:1996
EPA 624
EPA 82S08_L1996
EPA 8260B_2_'996
EPA 8270B_(9194)
EPA 8270B_{9/94)
EPA8270C 3 1996
EPA 8270C:::( 1996
EPA 82609_2_1996
EPA 82608_2_1998
PageS
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Good Standing
GOlla Standing
Good Standing
Good Standing
Good Standing
Good Slanding
Gooel Standing
Good Standing
Gooel Standing
Good Standing
Good Standing
Good Stending
Good Standing
Good Standing
Good Standing
Good Stending
Good Standing
Good stending
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Gooel Standing
Good Standing
GOOel StaMing
Good standing
Goed Standing
Good Standing
Good Standinv
Good Standing
Gooel Stending
Good standing
Gootl Stantling
Gootl Standing
Gooel Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
GoO<1 Standing
Good Standing
Good Standing
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
OKLAHOMA
DEPARTMENT Of ENVIRONMINTAl QUAliTY
•. .for a dean, DltnJCfive, prosperous Oklohomo
Laboratory 10: 0K00922
State Lab 10: 9517
Clean Water Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
Broken Arrow, OK 74012
(916)-251-2515
Certificate Number: 2009·105
Date of Issue: 91112009
expiration Date: 8/31/2010
Has demonstrated the capability to analyze environmental samples in accordance with Oklahoma Rules 252:301
and Is hereby granted CERTIFICATION FOR:
2.Seo-buIyJ-4,6·dinitropllenoJ (ONBP, Oinoseb)
2·St;lc-butyl-4,6-dinllropllenol (ONBP, Dlnoseb)
3-(Chloromethyl) pyridine hydrochloride
3-(Chloromethyl) pyridIne hydrochloride
3-(Chloromelhyl) pyJidine hydrochloride
3.(Chloromethyl) pyclcllne hydrochloride
3,3'·Olchloroben;tidine
3,3'·DlChlorobenitidine
3,3'·DJchIorOl!enitidine
3,3'·Dlchloroben;tidine
3,3'·Olchloroben4idine
3,3'·Dimelhoxybentidine
3,3'·DimelhoxybelUidine
3,3' ·Dimelhoxybanzidine
3.3'.0ImethOxyben4ldlne
3.3'·Dimethy1beJUkline
3.3'.0Imethylbenzidine
3.3'.Dlmethylbenzidine
3.3'·Ofmelhylbenzldlne
3-AmiflO.9-ethylcerbazole
3-Amlno-9-elhylcarbazole
3-Amlno-9-ethylcarbazole
3·AmlnO-9-ethyJcarbazole
3-Chloropropionilrile
3-Chloropropionitrile
3·Methylcholanthrene
3·Methylcholanlhrene
3-Melhylcholanthrene
3-Methylchofanthrene
3-Melhylphenol (m-Creso~
3·Methylphenol (m·Cresol)
3-Melh)'lphenol (m-Creso~
3-Melhylphenol (m-CresoQ
3-Nitroaniline
3-Nitroanlline
3-Nitroanilfne
3-Nilroanlllne
4,4'.000
4,4'.000
4,4'·000
4,4'·000
4.4'·000
4,4'.OOE
4.4'·OOE
4,4'·00E
EPA 82708_(9/114)
EPA 8270B_(9/94)
EPA 8270B_(9/114)
EPA 8270B_(9r94)
EPA 8270C_3_1996
EPA 6270C_3_1 896
EPA 626
EM 8270B_(9/94)
EPA 8270B_(9194)
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 82708_(9/94)
EPA 5270B_(9/94)
EPA 8270C_3_1998
EPA 6270C_3_1996
EPA 6270B_(9/~4)
EPA 8270B_(9/94)
EPA 8270C_3_19BS
EPA 8270C_3_1996
EPA 82708_(9/94)
EPA 62708_(9/94)
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 82608_2_1996
EPA 8260B_2_1996
EPA 82708_(9194)
EPA 8270B_(9/94)
EPA 827OC_3_1996
EPA 8270C_3_1996
EPA 8210B_(9/94)
EPA 8270B_(9194)
EPA 8270C_lU996
EPA 8270C_3_1996
EPA 8270B_(9/94)
EPA 82708_(9194)
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 625
EPA 8081 B_(11100)
EPA8081B_(11100)
EPA 8270C_3_1996
EPA 8270C_3_1998
EPA 625
EPA 8081 B_(11/00}
EPA 8081 B_(11100}
Page 7
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Good Standiog
GOOd Standing
Good Slending
Good Standing
GOod Stenalng
Good Standing
GOod Standing
Goot! Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Stllnding
Good Standing
Good Standing
Good Standing
Good Standing
GOod Standing
Good Standing
Good Standing
Good Stancling
Good Stancling
Goot! Standing
Good Sl;lndlng
Good Standing
GOod Standing
Good Standing
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Goot! Stending
Good Standing
Good Standing
Good Standing
Good Stanaing
Good Standing
GOod Standing
OKLAHOMA
O!PARTMENT Of ENVIRONMENTAL QUAlITY
••• fOT Q C/SOII, ottTodlve, prosperous Oklahoma
Laboratcry ID: OK00922
State lab 10: 9517
Clean Water Program
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
eroken Arrow, OK 74012
(916)-251·2515
CertIficate Number: 2009·105
Date of Issue: 9/1/2009
Expiration Date: 8/31/2010
Has demonstrated the capability to analyze environmental samples In accordance with Oklahoma Rules 252:301
and is hereby granted CERTIFICATION FOR:
<I,4'·DDE
4,4'·ODT
<I,4'·ODT
4,4'·ODT
<I,4'·DOT
4,4'·00T
4,<I'·Me1hylenebis(2·chloroanHlne)
4,4'.Melhyrenebis(2.chloroanlline)
4,4'-Melhylenebls(2-cllloroanlline)
4,4'·MelhylenebIB(2.chloroanlHne)
4.4'·Me\hyIenebI5(n, n-dimelhylan/llne)
4.4'·Methylenebls(n, n-dlmelt1ylanlllne)
4,4'·Methylenebls(n, n-dimelhylanlllne)
4,4'·Methylenebls(n, lHIimethylanHlne)
4,4'.Oxydianlnne
4,4'·Oxydlanlllne
4.4'-Oxydlanlllne
4,4'·Oxydianlline
4,6·0inltro-2·melhylpheno!
4,e-Dinitro-2-methylphenol
4,B-Dinitro·2·methylphenol
4.6-0ini1ro-2-methylphenol
4.B-0Initro-2·mell1ylphenol
4·Amlnoblphenyl
4-Amlnoblphenyl
4·Amlnoblphenyl
4·Aminobiphenyl
4-Bromophenyl phenyl ether
4-Bromophenyl phenyl ether
4-Bromophenyl phenyl ether
4-Bromophenyl phenyl ether
4-Chloro-l.2·phenylenediamlne
4-Chloro-1,2-phenylenediamlne
4-Chloro-1.2-phenylenediamlne
4-Chloro-1,2-phenylenediamlne
4-Chloro-l,3-phenylenediamine
+Chloro-l,3-phenylenediamlne
4-Chloro-l,3-phenylenedlamine
4-Chloro-l,3-phenylenediamlne
4.Chloro-3-rnethylphenol
4·Chlor0-3-methylphenol
4-Chloro-3-methylphenol
4-Chlor0-3-methylphenol
4-Chloro-3·methylpheno!
4-Chloroanlilne
EPA «I270C_3_l9ee
EPAG26
EPA 80818_(11/00)
EPA 8081B_(11I00)
EPA 8270C_3_19ee
EPA 8270C_3_1998
EPA 8270B_(9/94)
EPA 8270B_(911l4J
EPA B270C_:U9Q6
EPA «I270C_3_1996
EPA 8270B_(9/94J
EPA 82708_(9/94)
EPA 8270C_3_1QS8
EPA 8270C_3_1996
EPA 8270B_(S/94)
EPA 82708_(9/94)
EPA 8270C_3_1996
EPA 6270C_3_1996
EPA 825
EPA 82706_(9/94)
EPA 82708_(9194)
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270B_(9/94)
EF'A 8270B_(9/94)
EPA 6270C_3_1996
EF'A 8270C_3_1996
EPA 625
EPA 8270B_(9/94)
EF'A 8270B_(9/94)
EPA 8270C_3_1996
EPA 8270B_{9/(4)
EPA 82708_(9194)
EPA 8270C_3_1996
EPA 6270C_3_1996
EPA 82708_(9/94)
EPA «12708_(9/94)
EPA 6270C 3 1996
EPA 6270~S: 1996
EPA 625
EPA 82708_(9194)
EPA 8270B_(9194)
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 82708_(9194)
PageS
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Good Standing
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Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Slanding
Good Standing
Good Standing
Good Slendlng
GoDd Sianding
GoDd Standing
Good Standing
GoDd Standing
GoDd Standing
GoDd Stan~ng
Good Sianding
Good Standing
Good Sumdlng
Good Standing
Good Standing
Goo~ Standing
Good Standing
GoDd Stantling
Good Standing
Good standing
Good Standing
Good Standing
Good Standlng
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standln"
Good Standing
Good Slandlng
Good Staniling
OKLAHOMA
OIPARTMEtlT Of ENVIRONMENTAL QUAliTY
.•• for 11 dean, oII1aclive, prDSpeIl1IJS Oklahoma
Laboratory ID: OK0092.2
State LabID: 9517
Clean Water Program
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
S~ope of A~creditation
Outreach Laboratory
:311 North Aspen
Broken Arrow, OK 74012
(912)-251-2515
Certificate Number: 2009·105
Date of Issue: 9/1/2009
Expiration Date: 8/31/2010
Has demonstrated the c:apablUty to analyze environmental samples In accordance with Oklahoma Rules 252:301
and is hereby granted CERTIFICATION FOR:
4-Chloroanlllne
4-Chloroaniline
4-ChloroanlJine
4-Chloropllenol
4-Chloropllenol
4-Chlorophenol
4-Chlorophl!llyl4-~ elher
4-Chlorophenyl4-ni\ropheny! ether
4-Chlorophenyl phenyl ether
4-Chlorophenyl phenylelher
4-Chlorophenyl phenylelher
4-Chloropllenyl phenylether
4-Chlorophenyl phenylelher
4·Chlorotoluene
4·Chlorotoluene
4-Dlmethyl aminoazobenzene
4-Dlmethyl amlnoazobenzene
4.Dlmethyl amlnoazobenZllne
4-Dimethyl amlnoazobenzene
4-Melhyl·2-pentanone (MleK)
4-MeIhyl-2-pentenone (MlBK)
4-Melllyipheool (p-Cresol)
4-Metl1yIphenol (p-Cresol)
4-Methylphenol (p-Cresol)
4-MeJhylphenol (p-e reso!)
4-NHroanlllne
4-Nftroaniline
4-Nilroaniline
4-Nilro$lliline
4·Nllroblphenyl
4-NHroblphenyi
4-NRrobiphenyl
4-NHroblphenyl
4-NHrophenol
4-Nitrophenol
4-NHropllenol
04-NitlOphenol
4-Nitropheflol
5,5-0Iphenylhydantoin
5,S·Olphenylhydantoln
5,5-0Iphenylhydantoln
5,S·Oiphenylhydantoln
5-Chloro-2-methylanll1ne
5-Chloro-2-methylanWlne
5-Chloro-2·meItlylanlllne
EPA 82708_(9/94)
EPA 8270C_3_1996
EPA 827OC_:U998
EPA 825
EPA 8270C_3_19911
EPA 8270C_3_1998
EPA 8210C_3_1998
EPA 8210C_3_19ge
EPA 825
EPA 82108_(9/94)
EPA 8270B_(9/94)
EPA 827OC_3_HI98
EPA 8270C_3_1998
EPA 82608_2_1996
EPA 8260B_2_1998
EPA 8270B_(9/94)
EPA 8270B_(9194)
EPA 8270C_3_199B
EPA 8270C_lL 1998
EPA 8260B_2_1998
EPA 82608_2_1996
EPA 8270B_(9/94)
EPA 8270B_(91114)
EPA 8270C_3_1996
EPA 8210C_3_1996
EPA 82708_(9194)
EPA 6270B_(9/94)
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8210B_(9/94)
EPA 8270e_(9194)
EPA 8270C_~U996
EPA 8210C_3_1996
EPA 625
EPA 8270B_(9194)
EPA 82708_(9194)
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 62708_(9194)
EPA 82708_(9194)
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 82708_(9/94)
EPA 82708_(9/94)
EPA 8270C_3_1996
Page 9
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Good Standing
Good Stending
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standfng
Good Standin"
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good standiAg
Good Standing
Good Standing
Good Standing
Good Stancllng
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standin9
Good Standing
Good Standing
Good Standing
Good Standin9
Good Standing
Good standing
Good Standing
Good Slandin9
Good Standing
OKlAHOMA
DEfARIMENJ OF ENVIRONMENTAL QUALITY
....
.• .for Q cleon, OIlIOCliv8, prosperous Oklahoma
Laboratory 10: OK00922
State Lab 10; 9517
Clean Water Program
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
Broken Arrow, OK 74012
(918)-251.2515
~~r.$~ .. ~t..J? . J. •. " ~~ •• (J .' ...... I~izi~~+: \"~~~" .. • .~.v_~~~' 4) ,~ . . ....
\ .. : : : :. ' [00'...., ..
Certificate Number: 2009·105
Date of Issue: 91112009
Expiration Date: 8131/2010
Has demonstroted the capability to analyze environmental samples In accorclance with Oklahoma Rules 252:301
and is hereby granted CERTIFICATION FOR:
5-Chloro-2·methylanlllne
5·Nitroacenaphthene
5-Nilroacenapllthene
5-Nitroacenaph1hene
5-Nltroacenapllthene
5-Nitn>-O-anlsidine
5·Nilro-o-anisidine
&-NiIro-o-anisldine
5·NitfO.o.anisidine
5·Nitro-o-lOIuldlne
5-Nilfo.o.toluidine
5·Nilfo.o.toluidlne
5-NitfO.o.toILlKline
7,12-Oimlthylbenz(a) anthracene
7, 12.Dlmethylbenz(a) anthracene
7, 12-Dimethylbenz(a) anthracene
7,12-Dlmethylbenz(a) anthracene
a-a·Oimethylp/lenethylamlne
It-a-Olmelhylphenethylamlne
It-a-Dlmelhylp/lenethyiamlne
IH-Dimelhylphenethylamine
Acenaph1hene
Acenaph1hene
Acenaphthene
Acenaphthene
Acenaphlhene
Acenaph1hylene
Acenaphlhylene
Acenaphlhylene
AcenaptJthylene
AcenaptJthyiene
Acetone
Acetone
Acetone
Acetonitrile
Acetonitrile
Acetonitrile
Acetophenone
Acetophenone
Acetophenone
Acetophenone
Acidity, as CaC03
Acrolein (PropenaJ)
Acrolein (Propenal)
Acrolein (Propenal)
EPA 8270C_3_1906
EPA 82706_(9194)
EPA 82708_(9/94)
EPA 8270C_3_1998
EPA 8210C_3_1996
EPA 82108_(9/94)
EPA 82108_(9/94)
EPA 8270C_3_1996
EPA 8210C_3_1996
EPA 82708_(9194)
EPA 82706_(9194)
EPA 827OC_3_1996
EPA 827OC_3_199S
EPA 82709_(9/94)
EPA 82708_(9194)
EPA 8270C_3_1996
EPA 8270C_3_ HillS
EPA 82709_(9194)
EPA 82708_(9194)
EPA 8270C_3_11l1l6
EPA 821OC_3_1996
EPA 625
EPA 82708_(9/94)
EPA 82708_(9/94)
EPA 8270C_3_191l6
EPA 827OC_3_1996
EPA 625
EPA 8270B_(9I94)
EPA 82708_(9194)
EPA 8270C_3_1996
EPA 6270C_3_1996
EPA 624
EPA 82608_2_1996
EPA 62608_2_1996
EPA 824
EPA B2608_2_1996
EPA B2808_2_ 1996
EPA 6270B_(9/94)
EPA 6270B_(9/94)
EPA BZ70C_3_1996
EPA 8270C_3_1996
SM 18th EO 2310 8 (4A)
EPAB24
EPA 82608_2_1996
EPA 82608_2_1996
Page 10
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Good S~ndrng
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
GOO<I Standing
Good Standing
Good standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good standing
Good standing
Good standing
Good Standing
Good Standing
Good standing
Good standing
Good standing
Good standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Slanding
Good Standing
Good standing
Good Standing
Good standing
Good standing
Good Standing
Good standing
Good Standing
Good Slatlding
Good statlding
Good Standing
Good Standing
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
OKLAHOMA
D!PARTM£NT Of ENVIRONMUllAl OUAllT'1
••. for a crean. oll1l1ctive, prospeJilUS OkJohoma
Laboratory 10: OKOO922
State Lab ID: 9517
Clean Water Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
Broken Arrow, OK 74012
(918)-251-2515
Certificate Number: 20D!MD5
Date of Issue: 9/1/2009
Expiration Date: 8/3112010
Has demonstrated the capability to anal}'i:e environmental samples In accordance with Oklahoma Rules 252:301
and Is hereby granted CERTIFICATION FOR:
AcrylonItrile
Acrylonllrlle
AcrylonItrIle
Al2lchlor
Aladllor
Aldrin
Aldrin
Aldrin
Aldrin
Aldrin
Alkalinity n caC03
All 8270 comjXIunds
All 8270 COmjXlundS
Allyl alcohol
Allyl alcohol
Pollyl chloride (3·C,,10r0propene)
Allyl chloride (3-Chl0r0propene)
slpha-B He (alpha-Hexachlorocyclohexane)
alpha·SHC (alpha·Hexachlorocyclohexane)
alpha·SHC (alpha·Hexachlorocyclohexane)
alpha·SHC (alpha.Hexachlorocyclohexane)
alpha-BHC (a1pha·Hexachlorocyciohexane)
2Ilpha·Chlordane
alphlJoChlordane
alpha· Terpineol
Aluminum
Alumlflum
Aluminum
Amenable cyaflide
Amenable cyanide
Amenable cyanide
Amin<r.l:tOb~
Aminoazobenzene
Aminoazobeflzene
Aminoa:tObenzene
AmmoniaasN
Ammonia as N
Ammonia as N
AmmoniaasN
Anltazine
Anllazlne
Anifine
Aniline
Aniline
Aniline
EPA 624
EPA 82608_2_1996
EPA 8260B_2_1996
EPA 8061B_(11/00)
EPA 8081B_(11/00)
EPA 825
EPA 80818_(11/00)
EPA 8081 B_(11/00)
EPA 8270C_3_1996
EPA 8270C_3_1996
SM 2320 8 20th ED (199B)
EPA 8270_(9/86)
EPA 8270_(9185)
EPA 82eOB..2_1996
EPA 82608_2_199S
EPA 8260B..2_1 996
EPA 82608_2_1996
EPA 625
EPA 8081 8_(11/00)
EPA 8081 B_(11/00)
EPA 8270C_3_l99S
EPA 827OC3_1998
EPA 8081 B_C11JOO)
EPA 8081IU11/oo)
EPA 625
EPA 200.7_5_1998
EPA 601 OB_2_1 1196
EPA6010B 2 1996
EPA9010C--
EPA 9014_0_1996
SM 4S00·CN G 20th ED (1998)
EPA 82708_{9/94)
EPA 82708_(9194)
EPA 8270C_3_1996
EPA 8270C_3_1996
SM 4500·NH3 B 20th ED (199B)
SM ~o.NH3 B 20th ED (11198)
SM 4500-NH3 0 20th ED (1998)
SM 4500-NH3 0 20th ED (1998)
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 82708_(9194)
EPA 82708_(9/94)
EPA 8270C_3_1996
EPA 8270C_3_1996
Page 11
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Good Slendlng
Good Standing
Good Standing
Good Stending
Good Slending
Good Stuntllng
Good Stending
Good Standing
Good Slandlng
Good Sianding
Good Slanding
Good Standing
Good Standing
Good Slandtng
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Sianding
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Slanding
Good Standing
Good Standing
Good Slanding
Good Standing
Good'Standing
Good Standing
Good Standing
Good Standing
Good Standing
OKlAHOMA
DEPARTMfNl OF ENVIRONMENiAl QUAlITY
•.. (or 0 deon, at/IIJcffve, prosperous Oklahoma
laboratory 10: OK00922
State lab 10; 9517
Clean Water Program
Oklahoma Department of Environmental Quality
Laboratory A<:<:reditation Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
Broken Arrow, OK 74012
(918)-251-2515
Certificate Number: 2009-105
Oate ofIssue: 911/2009
Expiration Date: 6/31/2010
Has demonstrated the capability to analyze environmental samples In accordance with Oklahoma Rules 252;301
and is hereby granted CERTIFICATION FOR:
An1hIacene EPAS25 Nf'W Good Standing
Anthracene EPA 8270B_(9/94) S Good Sianding
Anthracene EPA 8270B_(9/94) Nf'W Good Standing
Anthracene EPA 8270C_3_1996 NPW GoCId Standing
Anthracene EPA 827OC_3_1996 S GOOII Standing
Antimony EPA 200.7_5_1998 NPW Good Standing
Antimony EPA 80108_2_1996 NPW Good Sianding
An1lmony EPA 8010B_2_1996 S Good Standing
Anamite EPA 8270B_(9/94) 5 Good Stamiing
Aramlte EPA 82708_(9194) NPW Good Standing
Aramite EPA 827OC_3_1996 NPW Good Standing
Aramite EPA 827OC_3_19aO S Good Standing
Argon-41 EPA 901 NPW Good Standing
Argon-41 EPA 901.1 S Good Standing
Algon-41 EPAS01.1 NPW Good Standing
Areclar-1018 (PCB-1016) EPA 8082A_J11100) S Gooi$ Standing
Araclor-1016 (PCB-1016) EPA 8082A...,(11/00) NPW Good Standing
Aroclor-1018 (PCB-1016) EPA 82rOC_3_1996 S Good Standing
Aroctor-1018 (pCB-10tS) EPA 82700_3_1996 NPW Good Standing
Aroclor-1221 (PCB-1221) EPA 8082A_(11100) NPW Gooo Standing
Aroc:lor-1221 (PCS-1221) EPA 8082A_(11100) S Good Standing
Aroclor-1221 (PCB-1221) EPA 8270C_3_1998 NPW Good Standing
Aroc:lor-1221 (PCB-1221) EPA 8270C_3_1998 S Gooo StandIng
Aroclor-1232 (PCB-1232) EPA 8082A_(11/00) S Good StandIng
Aroclor-1232 (PCB-1232) EPA 8082A_(11/00) NPW Good StandIng
Aroclor-1232 (PCB-1232) EPA 8270C_3_1996 S Good Standing
Aroctor-1232 (PCB-1232) EPA 827OC_3_1996 NPW Good Sianding
ArocIor-1242 (PCB-1242) EPA 8082A...(11100) Nf'W Good Standing
Aroelor-1242 (PCB-1242) EPA 8082A_(11I00) S Good Standing
Aroclor-1242 (PCB-1242) EPA 62700_3_'998 S Good Standing
Aroc1or-1242 (PCB-1242) EPA 8270C_3_'996 NPW Good Standing
Aroclor·1248 (PCB-1248) EPA 8082.4,..(11100) S Good Standing
Arocior·1248 (PCB-1248) EPA 8082.4,..(11/00) NPW Good Standing
Aroclor-1248 (PCB-1248) EPA 827OC_3_1996 S Good Standing
Aroclor-1246 (PCB-1248) EPA 827OC_3_1996 NPW Good Standing
Aroclor-1254 (PCB-1254) EPA 80B2A_(11/00) S Good Standing
Aroclor-1254 (PCB-1254) EPA B082A_(11I00) NPW Good Standing
Aroclor-1254 (PCB'1254) EPA 82700_3_1996 NPW Good Stand/nil
Aroclor-1254 (PCB-1254) EPA 8270C_3_1996 S Good Standing
Aroclor-1260 (pCB-1280) EPA 8OB2A_(11/00) S Good StandIng
ArocIor-1260 (PCB·1260) EPA 8082A_(11/00) NPW Good Standing
Aroclar-1260 (PCB-12BO) EPA 8270C_:U996 S Good Standing
Aroclor-1280 (PCB-1280) EPA 8270C_3_'996 NPW Gooi$ Standing
Al"l!lenlc EPA 200.7_5_1998 NPW Good Standing
Arsenic EPA6010B_2_'998 NPW Good Standing
Page 12
OKLAHOMA
DEPAR1,.,£HT Of ENVIRONMENlAl QUAl111
•• .for u dean, anracJiv8, prospefOlls Oklahoma
Laboratory 10: OK00922
State Lab 1D: 9517
Clean Water Program
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
Broken Arrow, OK 14012
(918)-251-2515
Certific;ate Number: 2009-105
Date of Issue: 911 ~OO9
expiration Date: 5/31/2010
Has demonstrated the capability to analyze environmental samples In accordance with Oklahoma Rules 2.52:301
and is hereby granted CERTIFICATION FOR:
Arsenic EPA6010B_2_1996 S Good Standing
Atratine EPA 625 NPW Good Standing
Atrazine EPA 827OC_3_1996 S Good Slanding
Awine EPA 827OC_3_1996 NPW Good Standing
Azinphos-melhyl (Guthlon) EPA 8270C_3_1996 S Good Standing
Azlnpllolf-methyl (GUlhlon) EPA 8270C_3_1996 NPW Good Standing
Bartlan EPA 8270C_3_1996 NPW Good Standing
Barban EPA 8270C_3_1996 S Good Standing
Barium EPA 200.7_5_1998 NPW Good Stancllng
Barium EPA 8010B_~1996 S Good Stancling
Barium EPA 6010B_2_1996 NPW Good Standing
Barium 133 EPA 901 S Good Standing
BarIum 133 EFA901 NF'W Good SlSnding
Barium 133 EPA 901 .1 S Good Standing
Barium 133 EPA 901.1 NPW Good Standing
Barium-140 EPA 901 NPW Good Standing
Barlum-140 EPA 901.1 S Good Standing
Barium·140 EPA 901.1 NPW Good Standing
Benzal chloride EPA 8270e_3_1ge6 S Good Standing
Benzal chloride EPA 827OC_3_1996 NPW Good Standing
Bemaldehytle EPA 8270C_3_1996 NPW Good Standing
Benzaldetlyde EPA 8270C_3_1995 S Good Standing
Benzene EPA 624 NPW Good Standing
Benzene EPA 8260B_2_1996 S Good Standing
Benzene EPA 8260B_2_1996 NPW Good Standing
Benzidine EPA 625 NPW Good Standing
Beniidine EPA 6270B_(9/94) S Good Standing
Benzidine EPA 8270B_(9/94) NPW Good Standing
Benzidine EPA 8270C_3_1996 S Good Standing
Senzla/ne EPA 8270C_3_199B NPW Good Standing
Benzo(a)antlllacene EPA 625 NPW Good Standing
Benzo(a)anlhracene EPA 8270B_(9194) S Good Standing
Benzo(a)anlhracene EPA 8270B_(9194) NPW Good Standing
Benzo(a)anlhracene EPA 8270C_3_1996 S Good Slandlng
Benzo{a)anlhracene EPA 827OC_3_1996 NPW Good Standing
8enzo(a)pyrene EPA 825 NPW Good Starnflll9
Benzo(a)pyrene EPA 8270B_(9/94) S Good Standing
Benzo(a)pyrene EPA 6270B_{9194) NPW Good Standing
Benzo(a)pyrene EPA 827OC_3_1996 NPW Good Standing
Benzo(a)pyrene EPA 827OC_3_1996 S Good Standing
Benzo(g,h,Operylene EPA 825 NPW Good Standing
8enzo(g,h,Operylene EPA 8270B_(9194) S Goad Standing
Benzu{g,h,l)pelylene EPA 82709_(9194) NPW GoodStand~
Benzo(g,h,Operylene EPA 8270C_3_1996 S Goad Standing
Benzo(g,h,i)perylene EPA 8270C_3_1996 NPW Good Stending
Page 13
OKLAHOMA
OE~ARlMENT Of ENVIRONMENTAL QUAlnV
••. for 11 detlll, ol11llclive, prosperous Qklohomo
Laboratory ID: OKOO922
state Lab ID: 9517
Clean Water Program
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
Scope of Accreditation
Outreach Laboratory
311 Ncrth Aspen
Broken Arrow, OK 74012
(918)-251-2515
Certificate Number: 2009-105
Date of Issue: 91112009
expiration Date: 613112010
Has demonstrated the capability to analyze environmental samples in accordance with OIdahoma Rules 252:301
and Is hereby granted CERTIFICATION FOR:
BenzoO)fluoranthene
BenzoOlfluoranthene
Benzo(k)fluoranthene
Benzo(k)fluoranthene
Benzo(k)fluoranLhene
Ben%O(k)f1uoranthene
Ben%OlblnuoranLhene
BenzolblnuoranLhene
BenzO[b)Auoranthene
Benzolb)AuoranLhene
Ben%O[b)Auoranthene
Benzoic acid
Benzo~acld
Benzoic acid
Benzoic acid
Benzoic acid
Benz.otrlc;hloride
Benzotrichloride
Benzyl alcohol
Benzyl alcohol
Benzyl alcohol
Benzyl alcohol
Benzyl Chloride
Benzyl Chloride
Benzyl chloride
Benzyl chloride
Beryllium
BerylUum
BerylDum
beta-BHC (beta-Hexachlorocyclohexane)
beta-BHC (beta-Hexachlorocyclohexane)
beta-BHC (beta-Hexachlorocyclohexane)
beta-BHC (beta-Hexacnlorocyclohexane)
beta-BHC (beta-Hexachlorocyclohexane)
bela-Proplolaclone
be!a-Proplolactone
Biochemical oxygen demand
Biphenyl
Biphenyl
Biphenyl
bis(2-Chl0r0elhoxy)methane
bis(2-Chloroetlloxy)mlltllane
bls(2-Chloroethoxy)methane
bis{2-Chloroethoxy)methlime
bi$(2-Chloroethyl) ether
EPA 8270C_3_1996
EPA 8270C_3_19S8
EPA 625
EPA 82708_(9194)
EPA 8270C 3 1998
EPA 82700:3:1998
EPA 825
EPA 82708_(9194)
EPA 82708_(9/94)
EPA 8270C_3_1996
EPA 6270C_3_1996
EPA 625
EPA 8270B_(9/94)
EPA 82708_(9194)
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA8270C 3 1996
EPA 8270C:3:1996
EPA 82708_(9/94)
EPA 82708_(9194)
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 821308_2_1996
EPA 8280B 2 1991)
EPA 8270C -3-1996
EPA 82700:3:1996
EPA 200.7_5_1998
EPA 6010B_2_1996
EPA 5010B_2_1996
EPA 625
EPA 80818_(11100)
EPA 80818_(11/00)
EPA 8270C_3_1998
EPA 8270C_3_1996
EPA 82808_2_1996
EPA 82608_2_1996
SM 5210 B 20th EO (1998)
EPA 625
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 82708_(9194)
EPA 82708_(9194)
EPA 8270C_3_19S8
EPA 8270C 3 1996
EPA625 --
Page 14
S
NPW
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S
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S
S
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S
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S
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NPW
NPW
Good Standing
Good Standing
Good Standing
Good Stanlfing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good SIanding
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Slanding
Good Standing
Good Standing
Good SIanding
Good Standing
Good SIaIlding
Good Slanding
Good Slandlng
: :,1 -~ ~:!!.9t'll:l --• t> --\
OKLAHOMA
DEPARTMENT OF ENVIRONMeNTAL QUAlITY
... ror 0 dean, offlaclive, prosperous Oklahoma
Laboratory 10: OK00922
State Lab ID: 9517
Clean Water Program
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
Broken Arrow, OK 74012
(918)-251-2515
Certificate Number: 2009-105
Date of Issue: 911/2009
Expiration Date: 8131/2010
Has demonstrated the capabiUty to analyze environmental samples In accordance with Oklahoma Rules 252:301
and is hereby granted CERTIFICATION FOR:
bis(2-Chloroethyl) ether EPA 8270B_(9/94) NPW Good Stand1ng
bis(2-Chloroethyl) ether EPA 8270B_(9/94) S Good Standing
bis(2-Chloroethy~ ether EPA 8270C_3_1996 NPW Good Standing
bls(2-Chloroethyl) ether EPA 8270C_3_1996 S Good Standing
bls(2-Chloroelhyl) sulfide EPA 8260B_2_1996 NPW Good Standing
bls(2-Chloroethyl) sulfide EPA 82608_2_1996 S Good Standlng
bls(2-Chlorolsopropyl) ether EPA 825 NPW Good Standing
bls(2-Chlorolsopropyl) elher EPA 8270B_(9J94) S Good Stan<ling
bls(2-Chlorolsopropyl) e1her EPA 8270B_(9/94) NPW Good Standlng
bfs(2-Chlorolsopropyl) ether EPA 8270C_3_1996 NPW Good Standing
bls(2-ChloroIsopropyij ether EPA 8270C_3_199S S Good Standing
bls(2-Ethylhexyl) phthalale (CEHP) EPA 825 NPW Good Stancling
lJls(2-EthyIhexyl) phthalate (DEHP) EPA 8270C_3_1996 S Good Standing
bls(2-Ethythexy!) phthalate (CEHP) EPA 8270C_3_1996 NPW Good Standing
Boron EPA200.7_S_1998 NPW Good StandIng
Boron EPA6010B_2_1996 S Goocl Standing
Boron EPA 0010B_2_1996 NPW Good Standing
Bromine-62 EPA 901 NPW Good Standing
Bromine-52 EPA 901.1 NPW Good Standing
Bromine-B2 EPA 901.1 S Good Standing
Bromoacetone EPA 8260B_2_1996 S Good Standing
Bromoacetone EPA 8260B_2_1996 NPW Good Standing
Bromobenzene EPA 8260B_2_1996 S Good Standing
Bromobenzene EPA 8260B_2_1996 NPW Good Standing
Bromochloromel1lane EPA 8260B_2_1996 NPW Good StandIng
BromOChloromelhane EPA 8260B_2_1996 S Good Standing
Bromodichloromathane EPA 624 NPW Good Stancllng
Bronnodichlorometl1ane EPA 8260B_2_1996 NPW Good Standing
BromodlchlOromelhane EPA 8260B_2_1996 S Good StandIng
Bromoform EPA 624 NPW Good Standing
Bromoform EPA 8260B_2_1996 S Good Stancling
Bromoform EPA 8260B_2_19913 NPW Goocl Standing
BromoxynD octanate EPA 8270C_3_1996 S Good Stantling
Bromoxyn~ octanate EPA 827OC_3_1996 NPW Good Standing
Butyl benzyl phthalate EPA 825 NPW Good Standing
Butyl be~ phthalate EPA 8270B_(9/94) NPW Good Standing
Butyl be~ phthalate EPA 8270B_(9/94) S Good Standing
Butyl benzyl phthalate EPA 827OC_3_1996 S Good Standing
Cadmium EPA 200.7_5_1998 NPW Good Standing
Cadmium EPA 601 OB_2_1996 S Good Slanding
CadmIum EPA6010B_2_1996 NPW Good Standing
Calcium EPA 200.7_5_1998 NPW Good StandIng
Calcium EPA6010B_2_1996 NPW Good Standing
Calcium EPA6010B_2_1S9S S Good Standing
Calcium-45 EPA 901.1 NPW Good Standing
Page 15
OKLAHOMA
DEPARTMENT OF ENVIRONMENTAl QUALITY
•.. for 0 deClll, otITocllve, prosperous Oklahoma
laboratory 10: OK00922
State lab 10: 9517
Clean Water program
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
Broken Arrow, OK 74012
(918)-251-2515
Certificate Number: 2009-105
Date of Issue: 9/112009
Expiration Date: 8/3112010
Has demonstrated the capabmty to analyze environmental samples in accordance with Oklahoma Rules 252:301
and Is hereby granted CERTIFICATION FOR:
CalCium-45
Caprolactam
Caprolactam
Csptafol
Captafol
Captafol
Captafol
Captan
Caplan
Carbaryl (Savin)
Carbaryl (Sevin)
Carbuole
Carbazole
Carbazole
Garbofutan (Furaden)
Carbofuran (Furaden)
Carbon disulfide
Carbon disulfide
Carbon tetrachloride
Carbon tetrachloride
Carbon tetrachlonde
Carbonaceous BOD. CBOD
Carbonyl sulfide
Carbonyl sulfide
carbophenothion
Carbophenot/llon
Ceriurn-144
Certum-144
Cesium-134
Ceslum-134
Ceslum-134
Cesium-134
Ceslum-137
Cesium·137
Cesium-137
Cesiurn-137
Chemical oxygen demand
Chloral hydrate
Chloral hydrate
Ctllordane (tech.)
Cltlordane (1ectI.)
Chlordane (tech.)
Chlordane (tech.)
Chlordane (tecll.)
Chlolfenvlnphos
EPA901.1
EPA 8270C_3_1998
EPA 8270C_3_1996
EPA 8081B_(11JOO)
EPA 80818-<11100)
EPA 8270C_3_19es
EPA 8270C_3_1998
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 825
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1998
EPA 8270C_3_1996
EPA 82608_2_1996
EPA B2ElOB_2_1996
EPA 824
EPA 6260B_2_1996
EPA 82608_2_1998
SM 6210 B 20th ED (1998)
EPA 82608_2_1996
EPA 8260B_2_1998
EPA 8270C_3_1998
EPA 82700_3_1996
EPA 901.1
EPA 901.1
EPA901
EPA 901
EPA 901.1
EPA 901.1
EPA 901
EPA 901
EPA 901.1
EPA 901.1
OlliER HACH 8000
EPA 82608..2-,1996
EPA 6260B_2_1998
EPA 625
EPA 8081B_(11/00)
EPA 8081B_(11/00)
EPA 8270C_3_1996
EPA 82700_3_1996
EPA 82700_3_1998
Page 16
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5
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Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good standing
Goocl SlanIIing
Good Slanding
Good Standing
Good Standing
Good standing
Good standing
Good Standing
Good Standing
Good standing
Good Standing
Good Standing
Good Standing
Good Standing
Good standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Slanding
Good Standing
Good Standing
Good Standing
Good Standlng
Good standing
Good Standing
Good Standing
Good standing
OKLAHOMA
DEPARTMENT OF ENVIRONMENTAL QUAlITY
•.. for 1/ dean, tlllTaclive, prosperous Okluhomo
laboratory ID: OK00922
State Lab 10: 9517
Clean Water Program
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
Broken Arrow, OK 74012
(918)-251-2515
Certtficate Number: 2009-105
Date of Issue: 91112009
Expiration Date: 8/31/201 ()
Has demonstrated the capability to analyze environmental samples in accordance with Oklahoma Rules 252:301
and is hereby granted CERTIFICATION FOR:
Clilorfenvinphos
Chlonde
Chloride
Chloride
Chlorine
Chlorine
Chlorobenzene
Chlorobenzene
Chlorobenzene
Chlorobenzllate
Chlorobenzllate
Chloroethane
Chloroelhane
Chloroethene
Chloroform
ChlorofolTTl
ChlorofolTTl
Chloroprene
Chloroprene
Chromium
Chromium
Chromium
Chromium VI
ChromJumVi
ChromJumVI
Chromium·51
Chromium·51
Chrysene
Chrysene
Chrysene
Chrysene
Chrysene
cis & trclns-1.2-0lchloroelhene
cis & Ir8ns-1.2-Oichloroe1llene
ci&-1.2-0Ichloroelhylene
cls-1.2-0ichloroethylene
cls·1.3-0ichloropropene
cl&-1.3-Dlchloropropane
cls-1,3-Dichloropropene
c1s-1,4-Dlchloro-2.butene
cis-1,4-Dichloro-2.butene
Cobalt
Cobalt
Cobalt
Cobalt 80
EPA 8270C_3_1998
ASTM 0512·898
SM 450O-CI C 20th ED (1998)
SM 4500-CIl> 6 19th ED (1995)
SM 4S00-CI G 20th ED (1998)
8M 4500-CI H 21st ED (2005)
EPA 624
EPA 82606..2_1998
EPA 82608_2_1996
EPA 8270C_3_1996
EPA 827OC_3_1998
EPA 624
EPA 82608_2_1996
EPA 8260B_2_1996
EPA 624
EPA 8260B_:U996
EPA 8260B_2_1996
EPA 8260B_2_1996
EPA 8260B_2_1998
EPA 200.7_5_1998
EPA 60108_2_1996
EPA 601 OB_2_1996
EPA 3060A_1_1996
EPA 7196A_1_1992
SM 3500·Cr 8 20111 EO (1998)
EPA 901.1
EPA 901.1
EPA 625
EPA 82708_(9/94)
EPA 82708_(9/94)
EPA 8270C_3_1996
EPA 827OC_3_1996
EPA 82608_2_1996
EPA 8260B_2_1996
EPA 8260B_2_1996
EPA 8260B_2_1996
EPA 624
EPA 8260B_2_1996
EPA 8260B_2_1998
EPA 8260B_2_1998
EPA 6260B_2_1996
EPA 200.7 _('U 998
EPA 6010B_2_1996
EPA 6010B_2_1998
EPA 901
Page 17
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Good Slanding
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good standing
Good Standing
Good Standing
Good Standing
Good SIanding
Good SIanding
Good Standing
GOO(! Standing
Good Sianding
Good Standing
Good Standing
Gooll Standing
Gooll Standing
Good Standing
Good Standing
Good Standinljl
Good Standing
Good standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
GOO(! Standing
Good SIanding
Good Standing
Good Standing
Good Standil'll/
Good Standing
Good Standing
Good standing
Good Sianding
Good Siandil'll/
Good Standing
Good Standing
KlAHOMA
DEPARTMENT OF ENVIRONMENTAL QU,I,\I1Y
... ror D dean, ottroc/ive, prosperous Oklahoma
Laboratory 10: OK00922
State Lab 10: 9517
Clean Water Program
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
Broken Arrow, OK 74012
(918)-251-2515
Certificate Number: 2009-105
Date ofIssue: 91112009
ExpIration Da te: 6/31/201 0
Has demonstrated the capabilitY to analyze environmental samples in accordance with Oklahoma Rules 252:301
and is hereby granted CERTIFICATION FOR:
CoballeD EPA 901 NPW Good Standing
Coball60 EPA 901.1 NPW Good Standing
Cobalt 60 EPA 1101.1 S Good Stancling
ConductivitY EPA 120.1_1962 NPW Good Standing
Conductivity SM 2510 B 2Gth ED (1998) NPW Good Standing
Copper EPA 2OD.7 _5_1998 NPW Suspended
Copper EPA 801 OB_2_1996 NPW Suspended
Copper EPA 60108_2_1996 S Suspended
Corrosivity (pH) EPA 9040B...2_1995 NPW GoOd Standing
Corroelvity (pH) EPA 9040B_2_1995 $ Good Standing
Coumaphos EPA 8270C 3 1996 $ Good Slanding
Coumaph()S EPA 827OC=3=1996 NPW Good Standing
Crotonaldehyde EPA 8260B_2_1996 S GOOd Standing
Crolonaldehyde EPA 8260B 2 1996 NPW Good Standing
Crotcxyphos EPA 8270C:'3:'1996 NPW Good Standing
Crotoxyphos EPA 827OC_3_1996 S Good Standing
Cyanide EPA 7.3.3.2_3_1996 NPW Good Standing
Cyanide EPA 7.3.3.2_3_'996 S Good Standing
Cyanide EPA 9010B_2_1996 NPW Good Standing
Cyanide EPA 9014_0_1996 NPW Good Standing
Cyarlide SM 4S00-CN C 20th ED (1998) NPW Good Standing
Cyanide SM 4SCo-CN E 20th EO (1998) NPW Good Stand'mg
CyciohelCane EPA 82608_2_1996 NPW Good Standing
delta-BHC EPA 625 NPW Good Slanding
delta-BHe EPA 8081 B_(11/oo) S Good Standing
delta-BHe EPA 8081 B_(11/00) NPW Good Standing
delia-SHe EPA 8270C 3 1998 S Good Standing
delta-BHe EPA 827OC:'3:1996 NPW Good Standin9
Demelon EPA 8270C_3_1996 S Good Standing
Demelon EPA 627OC_3_1996 NPW Good Standing
Demelono() EPA 827OC_3_1996 S Good Standing
Demetono() EPA 8270C_3_1996 NPW Good Standing
Oemeton-s EPA 827OC_3_1996 NPW Good Standing
Demelon-s EPA 827OC_3_1996 S Good Standing
DI(2-ethylhexyl)adipale EPA 625 NPW Good Standing
Di(2-ethylheXYl)adipate EPA 8270C 3 1996 NPW Good Standing
DI{2-ethyihexyl)adipate EPA 8270C:'3= 1996 S Good Standing
DI{2-ethylhexyl)phlhalate EPA 8270B_(9/94) NPW Good Standing
Oi{2-elhylhexyl)phlhalate EPA 8270B_(9/94) S Good Standing
DI(2-elhylhexyl)phthalale EPA 8270C_3_i996 S Good Standing
OI(2-elhylhexyl)phlhatate EPA 8270C_3_1996 NPW Good Standing
Ofallate EPA 8270C_3_199S NPW Good Standing
Olallate EPA 8270C_3_199S S Good Standing
Dibenz(a, h) acri(line EPA 827OC_3_1996 S Good Standing
Dibenz(a, h) acridine EPA 8270e_3_19B6 NPW Good Standing
Page 18
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
OKLAHOMA
DEPARTMENT OF ENVIRONMENTAL QUALITY
•.• for a clean, altlaclive, prosperous Oklahoma
Laboratory ID: 01<00922
State lab 10: 9517
Clean Water Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
Broken Arrow, OK 74012
(918)-251-2515
Certificate Number. 2009-105
Date of Issue: 9/112009
Expiration Date: 8/311201 0
Has demonstrated the capability to analyze environmental samples In accordance with Oklahoma Rules 252:301
and Is hereby granted CERTIFICATION FOR:
Olbenz(a,1) acridine
oibenz(a, j) acridine
Olbenz(a, )) acridine
Olbenz(a, j) acridine
Olbenz(a,h) anthracene
Oibenz(a,h) anthracene
01benz(a,h) anthracene
DIbenz(a,h) anthracene
Oibenz(a,h) anthracene
Dlbenzo(a, h) pyrene
Dlbenzo(a, tI) pyrene
Dlbenzo(a, I) pyrene
Dibenzo(a, I) pyrene
DIbenzo(a,e) pyrene
DIbenzO(a,e) pyrene
Dibenzo(a,e) pyrene
Dlbenzo(a.e) pyrene
Dibenzofuran
Oibenzoruran
Dibenzofuren
Dibenzoruran
Oibenzofuran
Olbromochloromethane
OIbromochloromelhane
01bromochloromelhane
Dibromocllioropropane
Olbromocl1loropropane
Dibromochloropropane
Olbromomeihane
Dlbromomethane
Olbulylphthatate _
Dlbutylphlharate
Dlchlone
Dichlona
Dlchlorodifluoromethane
Dlchlorodifluoromethane
Dichlorodifluoromethane
Dichloromethane (OeM. Methylene chloride)
Dlchloromethane (DCM, Methylene chlOride)
Dlehloromettlane (OeM. Methylene chloride)
Dichlorovos (DDVP, DichlorvOS)
Dichlorovos (DDVP, Dichlorvos)
Dierotophos
Dierotophos
Dieldrin
EPA 6270B_(9/94)
EPA 82708_(9/94)
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 625
EPA 82708_(9194)
EPA 8270B_(9/94)
EPA 8270C_3_1996
EPA 8270C_3_1998
EPA 8270C_3_1996
EPA 8270C_3_1998
EPA 821OC_3_1996
EPA 8270C_3_1996
EPA 82108_(9194)
EPA 82708_(9/94)
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 625
EPA 82708_(9/94)
EPA 82708_(9/94)
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 624
EPA 8280B_2_1996
EPA 82608_2_1996
EPA 624
EPA 8260B_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA8260B_~1996
EPA 6270C_:U995
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 6270C_3_1998
EPA 624
EPA 82608_2_1996
EPA 8260B_2_1996
EPA 624
EPA 8260BJ_1996
EPA 8260B_2_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_~U996
EPA 625
Page 19
5
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NPW
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NPW
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Good Standing
Good Slanding
Good Standing
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Good Standing
Good Standing
Good Sianding
Good Standing
Good Standing
Good Standing
Good StandIng
Good Standing
Good Standing
Good Slanding
Good Standing
Good Standing
Good Standing
Good Standing
Good Slanding
Good Slandlng
Good Standing
Good StandIng
Goocl Standing
Good Standing
Good Standing
Good S\<Indlng
Good Standing
Good Standing
Good Standing
Good Standing
Good standing
Good Standing
Good Standin9
Good Standing
Good Standing
Good Standing
Good StandIng
Good Standing
Good Standing
Good StandIng
Good Standing
Good Standing
it ,4!1'
.. ;~~~~ "'H~~ __ '~
OKLAHOMA
DEPARTMENT Of ENVIRONMENTAL QUAliTY
>
••. for 0 c/etJ(I, atl1Odive, prosperous Okfaliomo
Laboratory 10: OK00922
State Lab ID: 9517
Clean Water Program
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
Broken Arrow, OK 74012
(918)-251-2515
Certificate Number: 2009-105
Date of Issue: 911/2009
Expiration Date: 8/3112010
Has demonstrated the capability to analyze environmental samples In accordance with Oklahoma Rules 252:301
and is hereby granted CER11F1CATION FOR:
Dieldrin
Dieldrin
Dieldrin
Dieldrin
Dielhyl ether
Diethyl ether
Oiethyl ether
Diethyl phthalate
Olethyl phthalate
Oiethyl phthalate
Dlethyl phthelate
Dlethyl phthalate
Dielllyl sulrate
Diethyl sulrate
Diethy\ sulrate
Olethyl sulfate
Diethylstilbestrol
DlethylsHlbeSlrol
DIethylstilbestrol
Diethylstilbestrol
Dlhlldroeafrole
Dlhydrosafrole
Diltydtosafrale
DihydrosafrOle
Di-isopropylether (DIPE)
Dimethoate
Dimethoate
Dimethyl phthalate
Dimethyl phthalate
Dimethyl phthalate
Dimethyl phthalate
0i.n-bu\y1 phthalate
Di-n-butyl phthalate
DI-n-butyl phthalate
Di-n-butyl phthalate
DI-n-butyl phthalate
Dinocap
Dinocap
Oi·n-OClyI phthalate
Di-n-oClyI phthalate
D~n-octyl phthaillte
Dion-oClyI phthalate
Dion-oClyI phthalate
Dinogeb (2-sec-butyf.4.6-dlnltrophenol, DNBp)
Dlnoseb (2-sec-bUtyf.4.6-dinllrophenol. DNBF')
EPA 80618_(11/00)
EPA 80B18_(11/00)
EPA 8270C_3_1998
EPA 8270C_3_1996
EPA 624
EPA 82608_2_1996
EPA 82608_2_1996
EPA62!)
EPA 82708_(9194)
EPA 82708_(9/94)
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270B_(9194)
EPA 82708_(9194)
EPA 8270C_3_19S16
EPA 8270C_3_1996
EPA 82708_(9194)
EPA 82708_(9194)
EPA 8270C_3_1996
EPA 6270C_3_1996
EPA 8270B_(9194)
EPA 8270B_(9/94)
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 82608_2_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPAB25
EPA 8270B_(9/94)
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 625
EF'A 62708_(9/94)
EPA 82708_(9/94)
EPA 8270C_3_1998
EPA 8270C_3_'996
EPA 8270C_3_ 19ge
EPA 8270C_3_1996
EPA 825
EPA 82708_(9/94)
EPA 82708_(9194)
EPA 8270C_3_'996
EPA 827OC_:U99B
EPA 8270C_3_19ge
EPA 827DC_:iU9ge
Page 20
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Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Goat! Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
OKLAHOMA
OEPARTMENT OF ENVIRONMENTAL QUAlllY
•.• for a clean, aft1l1c/iY6, prqsp8lous OklohomD
Laboratory 10: OK00922
State Lab 10: 9517
Clean Water Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
Broken Arrow. OK 74012
(918)-251-2515
Certificate Number: 2009-105
Date of Issue: 9/1/2009
ExpIration Date: 813112010
Has demonstrated the capability to analyze environmental samples In accordance with Oklahoma Rules 252:301
and is hereby granted CERTIFICATION FOR:
Oioxathion EPA 8270C_3_1998 S Good Standing
Dlphenyl ether EPA 627OC_3_199B NPW Good Standing
Oiphenyl ether EPA 8270C_3_19S8 S Good Standing
Diphenylamine EPA 8270B_(9/94) S Good Standing
Diphenylamine EPA 8270B_(9I94) NPW Good St2Inding
Diphenylamine EPA 8270C_3_1996 NPW Good Standing
Diphenylamine EPA 827OC_3_1996 S Good Standlng
OisulfCton EPA 8270C_3_1996 NPW Good Standing
Disulfoton EPA 8270C_3_1996 S Good Standing
Endosulfan I EPA 625 NPW Good Standing
Endosulfan I EPA 8081 8_(11/00) S Good Standing
Endosulfan I EPA 60818_(11/00) NPW Good Standing
Endosulfan I EPA 8270C_3_1996 NPW Good Standing
Endosulfan I EPA 8270C_3_1996 S Good Standing
Endosulfan II EPA 625 NPW Good Standing
Endosulfen II EPA 8081 B_(11/oo) NPW Good Standing
Endosulfanll EPA 808t8_(1 t/OO} S Good Standing
Endosulfan n EPA 8270e_3_1996 NPW Good Standing
EnclosUifan II EPA 8270C_3_1996 S Good Standing
Emlosulfan sulfate EPA 825 NPW Good Standing
Endosulfan sulfate EPA 8OS1 B_{11/CO) S Good Standing
Endosulfan sulfate EPA 8QB1B_(11/00} NPW Good Standing
Endrln EPA 625 NPW Good Standing
Endrin EPA 8081 B_(11/00) S Good Standing
Endtin EPA 8081 B_(11/00) NPW Good Standing
Endrin EPA 8270C_3_199B NPW Good Standing
Endrln EPA 8270C_3_199B S Good Standing
Endrln aldehyde EPA 80816_(11100) S Good Standing
Endrln aldehyde EPA B081 B_(11/oo) NPW Good Standing
Endrln aldehyde EPA 8270C_3_1996 S Good Standing
Endrin ketone EPA 8081 B_(11/oo) NPW Good Standing
Ea1drin ketone EPA BOa1B_(1l/00} S Good Standing
Endrin kelone EPA 8270C_3_1996 NPW Good Standing
Endrin ketone EPA 8270C_3_1996 S Good Standing
EpichlorotJydrin (1-Chloro-2.3-epoqpropane) EPAB24 NPW Good Standing
EpichlorotJydtin (1·Chloro-2.3-ep011ypf'opane) EPA 8260EL2_1996 S Good Standing
EplchlOfotJydrin (1.Chloro-2.3-epoxypropane) EPA 8260B_2_1996 NPW Good Standing
EPN EPA 8270C_3_1998 S Good Standing
EPN EPA 6270C_3_1996 NPW Good Standing
Ethanol EPA 62608_2_1996 S Good Standing
Ethanol EPA 82608_2_1998 NPW Good Standing
Etllion EPA 827OC_3_1996 S Good Standing
Ethion EPA 8270C_3_1996 NPW Good Standing
Ethyl acetate EPA 8260B_2_1996 NPW Good Standing
Ethyl acetate EPA 6260B_2_1996 S Good Standing
Page 21
·1 . ~
... :~;~~;....:.: T""-'; • 'c. .. -t.:t,~ .
OKlAHOMA
DEPARTMENT OF ENVIRONMENTAL QUAliTY
••• (of Ii dean, attracJive, prosperous Oklahoma
laboratory ID: OK00922
State Lab ID: 9517
Clean Water Program
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
Broken Arrow, OK 74012
(918}-251-2515
Certificate Number: 2009-105
Date of1ssue: 91112009
Expiration Date: 8/31/2010
Has demonstrated the capability to analyze environmental samples in accordance with Oklahoma Rules 252:301
and is hereby granted CERTIFICATION FOR:
Ethyl carbamate (Urelllane)
Ethyl carbamate (Urethane)
Ethyl COIrbamate (Urelllane)
Ethyl carbamate (UreIIlane)
Ethyl methacrylate
Ethyl methacrylate
Ethyl methanesulfonate
Ethyl methanesulfonale
Ethyl methanesulfonate
Ethyl melhanesulfonate
Ethyl parathIon
Ethyl parathIon
Ethylbenzene
Ethylbenzene
Ethylbenzene
Ethylene C»dde
Ethylene oxide
Ettlyl-l-bulylelher (ETBE)
Ethyl-l-butylelher (ET6E)
Femphuf
Femphur
Fen8ulfothlon
Fensutfathlon
Fenthlon
Fenthion
Fluchlorafln
Fluchloralln
Fluoranthene
Fluoranthene
Fluoranlllene
F1uoranthene
Fluoranthene
Fluorene
Fluorene
Fluorene
Fluorene
Fluorene
Fluoride
F1uorida
Free liquid
Free liquid
Galaum-67
Gallium-57
gemma-BHC (Lindane, gamma-HexachlorocyclohexanE)
gamma-BHC (lindane, gamma-HexachlorocyclohexanE)
EPA 82708_(9/94)
EPA 82708_(9194)
EPA 6270C_3_1996
EPA 8270C_3_1996
EPA 8250B~1996
EPA 8250B_2_.1996
EPA 6270B_(9194}
EPA 8270B_(9I94)
EPA 827OC_3_1996
EPA 6270C_3_1996
EPA 8270C_3_1996
EPA 627OC_3_1996
EPA 624
EPA 8260B_2_1996
EPA82BOB_~1996
EPA 82506_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 6270C_3_1996
EPA 6270C_3_1996
EPA 6270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 827OC_3_199B
EPA 827OC_3_1996
EPA 625
EPA 82708_(9/94)
EPA 8270B_(9/94)
EPA 8270C_3_1996
EPA 8270C_:U996
EPAB25
EPA 82708_(9194)
EPA 6270B_(9/94)
EPA 8270C_3_1996
EPA 8270C_3_1996
8M 4500-F .. B 20th ED (1998)
8M 4500-FlJ C 20th ED (1998)
EPA 9095A_(12196)
EPA 9095A_(12196)
EPA 901.1
EPA 901.1
EPA 8270C_3_1996
EPA 6270C_3_1996
Page 22
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S
S
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Good Standing
Gooll Slanding
Good Standing
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Good Standing
Good Standing
GooC! Standlng
Good Slandlng
Good Standing
Good Standing
Good Standing
Good S\andlng
Good Standing
Good Standing
Good StandIng
Good Standing
Good Standing
Good Standing
Good Standing
Gcod Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Gcod Standing
Good Standing
Good Standing
Good Standing
Good StandIng
Good Standing
Good Standill9
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Gooc! Stendlng
OKLAHOMA
DEPARTMENT OF ENVIRONMENTAL QUAUn
•• , for a deol/, oflladive, prosperous Oklahoma
Laboratory ID: OK00922
state lab 10: 9517
Clean Water Program
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
Sroken Arrow, OK 74012
(918)-251-2515
Cert1f1cate Number: 2009-105
Date of Issue: 9/112009
Expiration Date: 8131/2010
Has demonstrated the capability to analyze ellVironmental samples in accordance with Oklahoma Rules 252:301
and Is hereby granted CERTIFICATION FOR: .
gamma'(;hlordane EPA 8081B_(11/00) S Good Standing
gamma.ChlOrdane EPA 80818_(11/00) NPW Good Standing
Gross alpha-beta EPA 900 NPW Good Standing
Gross aJpha-beta EPA 900 S Go<ld Standing
Gross alpha-beta EPA 9310_(9186) NPW Good Standing
Gross alphll-be\a EPA 9310_{i186) S ~Standlng
Gross gamma EPA901.1 S Good Standing
Gross gamma EPA 901.1 NPW Good Stemjing
Gross-aIpha EPA 931o_(9186) S Good Standing
Gross-alpha EPA 931 0_(9186) NPW Suspended
Gross-beta EPA 9310_(9186) S Good Standing
Gross-be1a EPA 931o_(9186) NPW Good Standing
Hardness EPA 130.2 • .1971 NPW Good Standing
Hardness SM 2340 C 20th ED (1998) NPW Good Standing
Hardness (calc.) ASTM 01126-86(92) NPW Good Standing
Heptachlor EPA 625 NPW Good Standing
HeptachlOr EPA 80818_(11/00) S Good Standing
Heptachlor EPA 8081 8_(11/00) NPW Good Standing
Heptachlor EPA 827OC_3_1996 NPW Good Standing
Heptachlor EPA 8270C_3_1996 S Good Standing
Heptachlor epoxide EPA 625 NPW Good Standing
Heptachlor epoxide EPA 8081 B_(11/00) NPW Good Standing
Heptachlor apOllide EPA 80S1 8_(11100) S Good Standing
HeptaChlor epoldde EPA827OC_~U996 S Good Standing
Heptachlor epoxide EPA 8270C_3_1996 NPW Good Standing
Hexachloroben:zene EPA 625 NPW Good Standing
Hexachlorobenzene EPA 62708_(9194) S Good Sianding
Hexachlorobel1:zene EPA 62708_(9/94) NPW Good Standing
Hexachlorobenzene EPA 827OC_3_1998 S Good Standing
Hexachlorobuladiene EPA 625 NPW Good Standing
Hexachlorobutadiene EPA 82608_2_1996 S Good Standing
Hexachlorobutadiene EPA 82608_2_1996 NPW Good Standing
HeKachlorobutadlene EPA 82708_(9194) NPW Good Standing
Hexachlorobutacliene EPA 82708_(9194) S Good Standing
HeKachlorobutadiene EPA 8270C_3_1996 NPW Good Standing
Hexachlorobutadfene EPA 8270C_3_1998 S Good Standing
Hexachlorocyclopentadlene EPA 625 NPW Good Standing
HexachlorOC1c1opentadlene EPA 82708_(9194) S Good Standing
Hexachlorocyclopentadiene EPA 82708_(9194) NPW Good Standing
Hexachlorocydopel1tadlene EPA 8270C_3_1996 S Good Standing
Hexachloroethane EPA 625 NPW Good Standing
Hexachloroethane EPA 8260B_2_1996 S Good Standing
Hexachloroethane EPA 8260B_2_1998 NPW Good Standing
Hexachloroethane EPA 82708_(9/94) S Good Standing
Hexachloroethane EPA 82708_(9194) NPW Good standing
Page 23
OKLAHOMA
DEPARTMENT OF ENVIRONMENTAL QUAUTY
••• for a deall, oflraclivs, prosperous Oklahoma
Laboratory TO: OK00922
State Lab 10: 9517
Clean Water Program
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
Broken Arrow, OK 74012
(918)-251-2515
Certificate Number: 2009-105
Date of Issue: 911/2009
Expiration Date: 8131/2010
Has demonstrated the capability to analyze environmental samples in accordance with Oklahoma Rules 252:301
and is hereby granted CElmFICAll0N FOR:
Hexachloroethane
Hexachloroethane
Hexachlorophene
Hexachlorophene
Hexachlorophene
Hexachlorophene
Hexachloropropene
Hexachloropropene
Hexachloropropene
Hexachloropropene
Hexachloropropene
Hexamelhylphosphoramlde (HMPA)
Hexamelhy!phosphoramide (HMPA)
Hydroquinone
Hydroquinone
Hydroquinone
Hydroquinone
Ignltability
!gnitability
Indeno(1.2.3-cd) pyrene
Indeno(1.2.3-ed) pyrena
Indeno(1,2.3-cd) pyrene
Indium-113m
Indium-113m
lodlne-123
lodlne-123
lodine-125
lodine-125
lodomethane (Methyl iodide)
lodomethane (Melhyllodlde)
Iridlum-192
lridium-192
Iron
Iron
iron
Iron-55
Iron-55
Iron-59
Iron-59
Isobutyl alcohol (2-Methyl-1-prOp2lnol)
Isobutyl alcohol (2-Methyl-1-propanol)
lsodrfn
Isodrln
I&ophorone
lsophorone
EPA 8270C 3 1896
EPA 8270C:3:1996
EPA 82708_(9/94)
EPA 62708_(8/94)
EPA 8270C_3_1996
EPA 8270C_~U9Sl6
EPA 626
EPA 82708_(9/94)
EPA 82708_(9/94)
EPA B270C_3_1998
EPA 8270C_3_1998
EPA 8270C_3_1996
EPA 8270C_3_19\!6
EPA 8270B_(9/94)
EPA 8270B_(9/94)
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 1010_(9/86)
EPA 1010_(9/86)
EPA 625
EPA 8270C 3 1996
EPA 8270C:3:1998
EPA 901.1
EPA 901.1
EPA 901.1
EPA 901.1
EPA 901.1
EPA 901.1
EPA 82608_2_1996
EPA 6260B_2_1996
EPA 901.1
EPA 901.1
EPA 200.7_5_1998
EPA 8010B_2_1996
EPA6010B_2_1996
EPA 901.1
EPA 901.1
EPA 901.1
EPA 901.1
EPA 8260B_2_1996
EPA 82608 2 1996
EPA 8270C:(1996
EPA 8270C 3 1996
EPA625 --
EPA 8270B_{9f94}
Page 24
S
NPW
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S
NPW
S
NPW
S
NPW
S
NPW
S
NPW
NPW
S
NPW
S
NPW
S
NPW
S
NPW
S
NPW
NPW
S
NPW
S
S
NPW
S
NPW
NPW
NPW
S
S
NPW
S
NPW
NPW
S
NPW
S
NPW
S
Good Sianding
Good Slanding
Good Standing
Good Stan(llng
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Slanding
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Slanding
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
OKLAHOMA
DEPARTMENT OF ENVIRONMENTAL QUAlm
_ •. for 0 dean, ot/rodive, prosperous Oklahoma
Laboratory 10: OKOO922
State Lab ID: 9517
Clean Water Program
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
Broken ArrrJW. OK 74012
(918)-251-2515
Certificate Number: 2009-105
Date of Issue: 911/2009
Expiration Date: &3112010
Has demonstrated the capability to analyze enllironmental samples In accordance with Oklahoma Rules 252:301
and Is hereby granted CERTIFICATION FOR:
Isophorone
lsoph<lrone
lsophorone
Isopropyl benzene
Isopropyl benzene
lsosafrole
Isoaafrola
Isosali'ole
Isosafrole
Kepone
Ke):ione
K'jeldBhI nittOgan
Kjeldahl nitrogen
Kjeldahl nitrogen· total
Kjeldahl nlllOgen -total
Krypton-85
Klypton-85
Lead
Le<ld
Lead
Lead-210
Lead-210
Lead-210
Lead-210
Leplophos
Leptopho$
m+p-xy1ene
m+p-xvlene
Magnesium
Magnesium
MagnesIUm
Matathion
Malathion
Maleic anhydride
Maleic anhydrfde
Maleic anhydride
Maleic anhydride
Maiononltrfle
Maiononltrfle
Manganese
Mangenese
Mangens,e
Mangenese-S4
Manganese-54
Manganlillle-54
EPA 8270B_(9/94)
EPA 8270C_3_1996
ePA 8270C_3_1996
EPA 82608_2_1996
EPA 8260B_2_1996
EPA 82708_(9/94)
EPA 82708_(9194)
EPA 8270C_3_1998
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
SM 4500-Norg B 20th EO (1998)
SM 4500-Norg B 20th EO (1998)
EPA 351.3_1978
EPA 351.3_1978
EPA 901.1
EPA 901.1
EPA 200.7_5_1998
EPA6010B_2_1996
EPA 6010B_2_1996
EPA 901
EPA 901
EPA 901.1
EPA 901.1
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 82608_2..1996
EPA 8260B_2_1991)
EPA 200.7_5_1998
EPA 6010B_2_1996
EPA 60108_2_1996
EPA 6270C_3_1996
EPA 8270C_3_1998
EPA 82708_(9194)
EPA 82709_(9/94)
EPA 8270C_3_'996
EPA 8270C_3_1996
EPA 82608_2_1996
EPA B280B_2_19Se
EPA 200.7_5_1998
EPA 6010B_2_1998
EPA8010B_2_1996
EPAB01
EPAB01
EPA 901.1
Page 25
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S
S
NPW
S
NPW
NPW
S
NPW
NPW
S
S
NPW
NPW
S
S
NPW
NPW
NPW
S
S
NPW
S
NPW
NPW
S
S
NPW
NPW
S
NPW
S
NPW
NPW
Good Standing
Good Standing
Good StandIng
Good Standing
Good Standing
Good Standing
Good Stand"1Ilg
Good Slamling
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good StandIng
Good StandIng
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Stanc:flllg
Good Standing
Good Standing
Good Standing
Good Stsndlng
Good Standing
Good Standing
Good Standing
Good Standing
Good Stsnding
Good standing
OKLAHOMA
DEPARTMENt Of ENVIRONMENTAL QUALITY
•• .for 0 ckon, ottlOctfVS, prosperous Ok/ohama
Laboratory 10: OK00922
State Lab ID: 9517
Clean Water Program
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
Broken Arrow, OK 74012
(918)-251-2515
Certlfic:ate Number: 2009-105
Date of Issue: 91112009
expiration Date: 8131/2010
Has demonstrated the capability to analyze environmental samples In accordance with Oklahoma Rules 252:301
and is hereby granted CERTIFICATION FOR:
Manganese-54
Mercury
Mercury
Mercury
Mestrenol
Mestlanol
Mestrenol
Mestlanol
MelhaoryJonilrile
MethacryJonltrile
Methanol
Methanol
Mell1apyrllene
Melhapyrilene
Methapyrilene
Methapyrllene
Methoxychlor
Methoxychlor
Methoxychlor
Methoxychlor
Methoxychlor
Methyl acetate
Meihyl acetate
Methyl bromide (Bromomethane)
Methyl bromide (Bromomethane)
Methyl bromide (Bromomethane)
Methyl chloride (Chloromethane)
Methyl chloride (Chloromethane)
Methyl chloride (Chloromethal'l$)
Methyl methaaylete
Methyl methaaylate
Methyl methanesulfonate
Methyl methanesultonate
Methyl methanesulfonate
Methyl methanesulfonata
Methyl pat81hion (parethlon, methyl)
Methyl parathion (Parathion. methyl)
Methyl tert-butyl ether (MTBE)
Methyl tert·butyl ether (MTBE)
Methyl tert-butyl ether (MTBE)
Methylcyclohexane
Methylcyclohaxane
Methylene chloride
Methylene chloride
Methylene chloride
EPAS01.1
EPA 246.1_3_1994
EPA 7470A.J_1994
EPA 7471B_(1/98)
EPA 8270B_(9/94)
EPA 8270B_(9/94)
EPA 8270C_3_1996
EPA82700 3 1995
EPA 8260Bj=-1998
EPA 8260B_2_1998
EPA 82808_2_1996
EPA 8260B_2_1996
EPA 8270B_(9194)
EPA 82708_(9/94)
EPA 827OC_3_1996
EPA 8270C_3_1996
EPA 626
EPA 8081 8_(11/00)
EPA8081B_(111OO)
EPA 8270C 3 1996
EPA 827OC=3=1996
EPA 82609_2..1996
EPA 8260B_2_1996
EPA 624
EPA 82608_2_1S96
EPA 8260B_2_1998
EPA 624
EPA 8260B_2_1996
EPA 8260B_2..1996
EPA 82608_2_1996
EPA 82609_2_1996
EPA 82709_(9/94)
EPA 82708_(9/94)
EPA 8270C_3_1998
EPA 82700_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 624
EPA 82608_2_1996
EPA 82608_2_1996
EPA 8260B_2_1996
EPA 8260B_2_1996
EPA 624
EPA 8260B_Z_1996
EPA 8260B_2_1998
Page 26
S
NPW
NPW
S
S
NPW
S
NPW
NPW
S
S
NPW
NPW
S
NPW
S
NPW
NPW
S
S
NPW
S
NPW
NPW
NPW
S
NPW
NPW
S NPW
S
S
NPW
NPW
S
S
NPW
NPW
S
NPW
S
NPW
NPW
S
NPW
Good Standing
Good Standing
Good Standing
Good Standing
Good Standln"
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good StandIng
Good Standing
Good Standin"
Good Standing
Good Standing
Good Standing
Good Standing
Good standing
Good Standing
Good StandIng
Good Standing
Good Standing
Good StandIng
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good standing
Good Standing
Good Standing
Good Standing
Goo!! Standing
Good Standing
Good standing
Good Standing
Good Standing
OKLAHOMA
DEPARTMENT OF iNVIRONMENTAI QUALITY
__ • frH a (/etm, attractive, (JIOSPSrolJS Oklahoma
laboratory 10: OK00922
State LabID: 9517
Clean Water Program
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
Broken Arrow, OK 74012
(916)-251-2515
Certificate Number: 2009-105
Date of Issue: 911/2009
expiration Date: 8131/2010
Has demonstrated the capability to analyze environmental samples in accordance with Oklahoma Rules 252:301
and Is hereby granted CERTIFICATION FOR:
Mevinphos EPA 8270C_3_1996 S Good Standing
MevinphO$ EPA 13270C_3_1996 NPW Good Standing
Mexacarbate EPA 8270C_3_1996 S Good Standing
Mexacarbate EPA 8270C_3_1998 NPW Good Standing
~rex EPA 8270C_3_1996 S Good Standing
Mrex EPA 8270C_3_1996 NPW Good Slanding
Molybdenum EPA 200.7_5_1998 NPW Good Standing
Molybdenum EPA6010B_~1996 S Good Standing
Molybdenum EPA6010B_2_1996 NPW Good Standing
Molybdenum-99 EPA 901.1 S Good Standing
Molybdenum-S9 EPA901.1 NPW Good Standing
Monocrotophos EPA 827OC_3_1998 NPW Good Standing
Monoerotopnos EPA 827OC_3_1998 S Good Standing
m-Xylene EPA 8260B_2_1996 NPW Gaod Standing
m-Xylene EPA 82608_2_1996 S Good Standing
n. n-dimethyl rormamide EPA 8270C_3_19BB NPW Good Standing
n. n-dimethyl formamide EPA 8270C_3_1996 S Good Standing
N8IecI EPA 6270C_3_1996 S Good Slanding
Naled EPA 8270C_3_1996 NPW Good Slanding
Naphthalene EPA 624 NPW Good Standing
Naphthalene EPAB25 NPW Good Stending
Naphlheiene EPA 8260B_2_199.6 NPW Good Standing
Naphthalene EPA 82608_2_1996 S Good Standing
Naphthalene EPA 8270B_(9/94) S Good Standing
Naphthalene EPA 82708_(9/94) NPW Good Standing
Naphthalene EPA 8270C_3_1996 NPW Good Slanding
Naphthalene EPA 8270C_3_1998 S Good Standing
n-Butyl alcohol EPA 82eOB_2_1996 S Good Standing
n-Butyl alcohol EPA 82608_2_1996 NPW Good Standing
n-Bu\ylbenzene EPA 82608_2_1998 S Good Standing
n-Butylbenzene EPA 82608_2_1996 NPW Good Standing
n-Decane EPA 625 NPW Good Standing
n-Oeeane EPA 8270e_3_1996 NPW Good Standing
n-Decene EPA 8270C_3_1996 S Good Standing
n-Docosane EPA 625 NPW Good Sianding
n-Oodecene EPA 625 NPW Good Standing
n-Elcoaane EPA 625 NPW Good Standing
n-Hexaclecane EPA 625 NPW Good Standing
Nickel EPA 200.7_5_1996 NPW Good Standing
NICkel EPA6010B_2_1996 NPW Good Standing
NICkel EPA 80108_2_1996 S Good Standing
Nicoline EPA 82708_(9/94) S Good Standing
Nlootine EPA 8270B_(9/94) NPW Good Standing
NiCOline EPA a270C_3_19Ba NPW Good Standing
NiCOline EPA 8270C_3_1996 S Good Standing
Page 27
OKLAHOMA
DEPARTMENT Of ENVIRONMENTAL QUAliTY
, , • for 0 cfeon, oItroclive, prospeTOUS Oklahoma
Laboratory 10: OK00922
State Lab 10: 9517
Clean Water Program
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
6rokenArrow, OK 74012
(918)-251-2515
~~~. ~'~"":,., ~·~~Lf:.'~'~ 1[(7'I!m" .\£l~,-' •• . : . -.; .~ ... ~
;.... ~'" <) "',,~~ .. 1". r • ~ ~. ~ .'.
!';:' .:-''-. ..
Certificate Number: 2009·105
Date of Issue: 9/1/2009
expiration Date: 8131/2010
Has demonstrated the capability to analyze environmental samples In accordance with Oklahoma Rules 252:301
and is hereby granted CERTIFICATION FOR:
Nitrate
Nltrate
Nitrate
Nitrate
NitrateasN
Nltrate8s N
Nitrite
Nitrobenzene
Nitrobenzene
Nitrobenzene
Nitrobenzene
Nitrobenzene
Nitrobenzene
Nitrobenzene
Nitrobenzene
Nitrofen
Nilrofen
Nllroquinoilne-1-oxide
Nltroqulnollne-1-oxide
Nllroquinollne-1-oxide
Nitroqulnoline-1oOldde
n.Nilrosodlelhylamine
n·Nitroscdlelhylamine
n-Nilrosodlelhylamlne
~Nitrosodlelhylamlne
n-Nltrosodlethylamlne
n-Nitroeodlme\hylamine
~Nltrosodlme\hylamlne
n-Nilrosodimelhylamine
n.Nltrosodlmlilhylamine
n-Nltrosodlmelhylamlne
n-Nilroso-dkl-bulylamine
n-Nitroso-dl-n-bulylamfne
n-Nltros()-dl-n-butylamlne
n-Nl\roso-dl-n-butyiamine
n-Nltroso-dl-n-butylamlne
n-Nltroso-di-n-butylamine
n-N!troso.dl-n-butylamlne
n-Nitrosodl-n-propylamlne
n-NIIro60dl-n-propylamlne
n-NlIrosodl-n-propylamlne
n-Nilrosodl-n-propylamlne
n-Nltrosodl-n-propylamlne
n-Nltrosodlphenylamine
n-Nitrosodiphenylamlne
EPA 9210_0_1996
EPA 9210_o_1996
SM 4500-N031t D 20th ED (1998)
SM 4500-NOa» D 20th ED (1998)
EPA 352.1_1971
EPA 352.1_1971
SM 450O-NOa~ E 20th ED (1998)
EPA 624
EPA 625
EPA 62608_2_19116
EPA 62608_2_1996
EPA 82708_(9194)
EPA 82706_(9194)
EPA 6270C_:U996
EPA mOC_3_1996
EPA 8270C_3_1996
EPA 8270C_3_199a
EPA 82706_(9194)
EPA 82708_(9194)
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 625
EPA 8270B_(9194)
EPA 82708_(9194)
EPA 8270C_3_1996
EPA 8270C_3_1996
EPAG25
EPA 8270B_(9T94)
EPA 8270B_(9/94)
EPA 827OC_3_1996
EPA 8270C_3_1geB
EPA 625
EPA 82606_2_1996
EPA B260B_2_19SB
EPA 82708_(9194)
EPA 8270B_(9194)
EPA 8270C_3_199B
EPA 8270e_3_1996
EPA 625
EPA 82708_(9194)
EPA 82708_(9/94)
EPA 8270C_3_1998
EPA 8270C_3_1996
EPA 625
EPA 82708_(9/94)
Page 28
NPW
S
NPW'
S
S
NPW
NPW
NPW
NPW
S
NPW
S
NPW
NPW
S
5
NPW
NPW
S
NPW
S
NPW
S
NPW
S
NPW
NPW
S
NPW
S
NPW
NPW
NPW
5
S
NPW
NPW
S
NPW
S
NPW
S
NPW
NPW
NPW
Good Standing
Good Standing
Good Standing
Good Staniling
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Stancling
Good StandIng
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good SWK\ing
Good standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
GOOd Stanillng
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standtng
Good Standing
Good Standing
Good Standing
Good Standing
OKLAHOMA
nEPARTMENT Of ENYIRONMENTAI QUALITY
.. .for a clean, alfrac!ive, prosperous Oklahomo
Laboratory 10: OK00922
State Lab ID: ·9517
Clean Water Program
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
Broken Arrow, OK 74012
(918)-251-2515
Certificate Number: 2009·105
Date of Issue: 911/2009
Expiration Date: 8131/2010
Has demonstrated the capability to analyze environmental samples In accordance with Oklahoma Rules 252:301
and Is hereby granted CERTIFICATION FOR: ..
n-Nltrosodlphenylamine
n-Nllrosodiphenylamine
n-Nltrosodiphenylamine
n-NitrOsodlpropylamine
n-Nitrosodlpropylamine
n-Nitrosomelhylethalamlne
n·Nitrosomethylethe.lemllle
n-Nitl'Osonnelhylethe.lamine
n.Nitrosomethylethalamine
n-Nitrosomorpholine
n-Nitrosomotpholine
n-Nitrosomorphollne
n-Nltrosomorpho6ne
n·Nitrosopipel1dine
n-Nitrosoplper1dlne
n.Nitrosoplperidine
n-Nilrosoplperldine
n-Nitrosopyrrolldlne
n-Nitrosopyrrolldine
n·Nltrosopyrrolldlne
n-Nltrosopyrrolldlne
rHlctade<:a118
n-Octadecane
n.Qctadecane
n-propylamlne
n-propylamlne
n-Telradecane
0,0,0. Trlethyl phosphorothioate
0,0,0-Triethyl phosphorothioate
o-Anisidine
o-Anisidine
o-AnislcUne
o-Anlsidine
Octamelhyl pyrophosphOramlde
Octamethyl pyrophosphoramlde
011 & Grease
011 & Grease
Orthophosphate as P
o-Toluldlne
0-Toluidine
0-Toluidine
o·Toluidlne
o-Toluidine
0-Toluidine
Oxygen, dissolved
EPA 82708_(9/94)
EPA 8270C_3_1996
EPA 8270e_3_1998
EPA 8270C_3_199B
EPA 8270C_3_1996
EPA 82708_(9194)
EPA 82708_(9/94)
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270B-19194)
EPA 8270B_(9/94)
EPA 8270C_3_1996
EPA 82700_3_1996
EPA 82708_(9194)
EPA 8270B_(9/94)
EPA 82700_3_1996
EPA 82700_3_1996
EPA 8270B_{9(94)
EPA 8270B_(9I94)
EPA 827OC_3_1996
EPA 827OC_,U996
EPA 625
EPA 827OC_3_1996
EPA 82700_3_1996
EPA 82608_2_1996
EPA 8260B_2_1996
EPA 625
EPA 627OC_3_1996
EPA 8270C_3_1996
EPA 8270B_(9/94)
EPA 8270B_(9/94)
EPA 8270C_3_1996
EPA 8270C_3_198&
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 1664A
SM 5520 8 20th ED (1998)
SM 4500-P E 201h ED (1998)
EPA 8260B_2_1996
EPA 82608..2 • .1996
EPA 82708_(9194)
EPA 8270B_(9194)
EPA 8270C_3_1996
EPA 627DC_:U998
SM 4500.Q G 20th EO (1998)
Page 29
S
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S
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Good Standing
Good Standing
Good Standing
Good standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Sianding
Gooel Slandlng
Good Slanding
Good Slanding
Gooel standing
Good Slending
Good Standing
Gooel Standing
Good Slandlng
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Slanding
Gooel Standing
Good standing
Good Slandlng
Good Standing
Good standing
Good Stanellng
Good Slaneling
Good Standing
Good Slanding
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standlng
Good Slending
Good Standing
Good Slanding
Good Standing
Good Standing
Good Standing
OKlAHOMA
DEPARTMENT OF ENVIRONMENTAL QUALITY
••• fOl /I clam, Oll1odire, prosperous Oklahoma
laboratory ID: OK00922
stare Lab ID: 9517
Clean Water Program
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
Broken Arrow, OK 74012
(918)-251-2515
;','i\:. ~~ .• ~~".I.":~~ II> ....... .
. ~~.~~~. >.:;
lil' .. ~r'r" .... \: , ' . . ' .. ~'" .. ' ~.~" . .... ~. }.a;#., • " ,-.. . \/. ', ... " .
• , <)7f!
Certificate Number: 2009-105
Date of IsstJe: 9/112009
Expiration Date: 8/3112010
Has demonstrated the capability to analyze environmental samples in accordance with Oklahoma Rules 252:301
and Is hereby granted CERTIFICATION FOR:
Oxygen. dissolved SM 4500'() G 21st ED (2005) NPW Good Slanding
o-Xylene EPA 8260B_2_1996 NPW Good Slanding
o-Xylene EPA 82608_2_1 ees S Good Standing
Paraldehyde EPA 82608_2_199s NPW Good Standing
Paraldehyde EPA 82608_2_1996 S Good Standing
Parathion EPA 8270C_3_1996 S Good Standing
Parathion EPA 8270C_3_1996 NPW Good Standing
p.Berl%oqulnone EPA 8270B_(9/94) S Good Standing
p.Benzoquinone EPA B27OC_3_1996 NPW Good Standing
p.Benzoquinone EPA 8270C_3_1996 S Good Standing
p.Cresidine EPA 82708_(9/94) NPW Good Standing
p.Cresidine EPA 82709_(9194) S Good Standing
p.cresidine EPAB270C_3_19gs S Good Standing
p.Cresldine EPA 8270C_3_1996 NPW Good Slanding
p.Oioxane EPA 624 NPW Good Standing
p.D1oxane EPA 82608_2_1998 S Good Standing
p.Dloxane EPA 82608_2_1996 NPW Good Standing
PentachlOrobenzene EPA 82708_(9194} NPW Good StandIng
Pentachlorobenzene EPA 82708_(9/94) S Good Standing
PentaChlorobenzene EPA 8270C_3_1996 NPW Good Standing
Pentachlorobenzene EPA 8270C_3_1996 S GootS Standing
Pentachloroethane EPA 625 NPW Good Standing
Penlachloroethan& EPA 82608_2_1996 S Gooll Standing
Pentachloroethane EPA 82608_2_1996 NPW GootS Stending
Pentachloronltrobenzene EPA 82708_(9/94} S Good Standing
Penlachloronltrobenzene EPA 82708_(9/94) NPW Good StandIng
Pentachloronllrobenzene EPA 8270C_3_1996 NPW Good Standing
Pentachloronltrobenzene EPA 8270C_3_1996 S Good Slanding
Pentachlorophenol EPA 625 NPW Good Standing
Pentachlorophenol EPA 82708_(9194) S Good Standing
PentaChlorophenol EPA 8270B_(9194) NPW Good Standing
Pentachlorophenol EPA 8270C_3_1996 S Good Standing
Pentachlorophenol EPA 8270C_3_1996 NPW Good Standing
pH EPA 1l040A_(9194) NPW Good Standing
pH EPA9045D S Good Standing
pH SM 4500·H+ B 20th ED (1998) S Good Standing
pH SM 4500·H+ B 20th ED (1998) NPW Good Standing
Phenacetin EPA 8270B_(9194) S Good Standing
Phenacetin EPA 82708_(9194) NPW Good Standing
Phenacetin EPA 827OC_3_t996 S Good Standing
Phenacetin EPA 8270C_3_199a NPW Good Standing
Phenanthrene EPA 625 NPW Good Standing
Phenanthrene EPA 82708_(9194) NPW Good Standing
Phenanthreile EPA 8270B_(9/94) S Good Standing
Phenanthrene EPA B27OC_3_1998 NPW Good Standlng
Page 30
OKLAHOMA
OEPARTMENT Of ENVIRONMENTAl QUAtIly
••. for 0 deon, IJltTaclivB, prospsrous Oklahoma
laboratory ID: OK00922
state Lab ID: 9517
Clean Water Program
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
Broken Arrow. OK 74012
(918}-251-2515
Certificate Number: 2009-105
Date of Issue: 9/1/2009
Expiration Date: 8131/2010
Has demonstrated the capability to analyze environmental samples in accordance with Oklahoma Rules 252:301
and Is hereby granted CERTIFICATION FOR:
PIlenanthrene EPA 827OC_3_1996 S Good Standing
Phenobarbital EPA 8270B_(9/94) NPW Good Standing
Phenobarbital EPA 82708_(9/94) S Good Standing
Phenobarbital EPA 8270C_3_1996 NPW Good Standing
Phenobarbital EPA 827OC_3_199E1 S Good Standing
Phenol EPA 625 NPW Good Standing
Phenol EPA 8270B_(9/94) S Good Standing
Phenol EPA 8270B_(9I94) NPW Good Standing
Phenol EPA 8270C_3_1996 NPW Good Standing
PIlenol EPA 8270C_3_1996 S Good Standing
PhoI'ate EPA 8270C_3_1996 S Good Standing
Phorate EPA 8270C_3_1996 NPW Good Standing
PhOsalone EPA 8270C_3_1996 NPW Good Stending
PhOSalone EPA 8270C_3_1996 S Good Standing
PhOsmet (Imidan) EPA 8270C_3_1996 S Good Standil'lll
Phosmet (Imil:fan) EPA 8270C_3_1996 NPW Good Standing
Phosphamidon EPA 8270C_3_1996 NPW Good Standing
PtIOspllamldon EPA 8270C_3_1996 S Good Standing
Phosphorus. total EPA 6010B_2_1996 S Good Standing
Phosphorus, Iotal EPA 601 OB_2_1995 S Goo(l Standing
PhOSphorus. total EPA 6010B_2_1996 NPW Good Standing
Phosphorus, total SM 4500-P 8 Ii 20th EO (1998) NPW Good Standing
Phosphorus, tolal SM 450O-P E 20th ED (1998) NPW Good Standing
Phthalic anhydri(la EPA 82708_(9/94) NPW Good Standing
Phthalic anhydride EPA 8270B_(9/94) S Good Standing
Phthalic anhydride EPA 8270C 3 1996 NPW Good Standing
Phthalic anhydride EPA 8270C:3: 1996 S Good Standing
Plperonyl sulfoxide EPA 8270B_(9/94) S Good Standing
Piperonyl sulfoxide EPA 82708_(9/94) NPW Good Standing
Plperonyl sulfoxide EPA 827OC_3_1996 NPW Good Standing
Plperonyl sulroxide EPA 8270C_3_1996 S Good Standing
p.lsopropyllOluene EPA 624 NPW Good Standing
P.!sopropylloluene EPA 8260B_2_1996 NPW Good Standing
p.lsopropyitotuene EPA 82608_2_1996 S Good Standing
Potassium EPA 200.7_5_1998 NPW Good Standing
Potassium EPA6010B_2_1996 NPW Good Standing
Potassium EPA6010B_2_1998 S Good Sianding
Pronamide (Kerb) EPA 82708_(9/94) NPW Good Standing
Pronamide (Kerb) EPA 8270B_(Ql94) S Good Sianding
Pronamida (Kerb) EPA 8270C_3_1996 S Good Standing
Pronamide (Kerb) EPA 8270C_3_1996 HPW Good Standing
propargyl alootlOl EPA 82606_2_1996 NPW Good Standing
Propionitrile (EIIlyI cyanide) EPA 82608_2_1996 NPW Good Standing
Propylthiouracil EPA 82708_(9f94) S Good Standing
Propylthiouracil EPA 82708_(9/94) NPW Good Standing
Page 31
. ~
i:;:~'\t(. -. "h.. 'p__ ..
OKLAHOMA
DEPARiMENT OF ENVIRONMENTAL QUAlITY
_, _ for 11 de/1tl, ottrllctive, prOS{J8f01IS Oklahoma
Laboratory 10: OK00922
State Lab 10: 9517
Clean Water Program
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
Broken Arrow. OK 74012
(918)-251-2515
Certificate Number: 2009-105
Date of Issue: 9/1/2009
expiration Date: 8/3112010
Has demonstrated the capability to analyze enVironmental samples In accordance with Oklahoma Rules 252:301
and Is hereby granted CERTIFICATION FOR:
Propylthiouracil EPA 8270C_3_1996 NPW Good StandIng
Propylthiouracil EPA 8270C_3_1996 S Good Standlng
p-Xylene EPA 8260B_2.J 996 NPW Good Standing
p-Xylene EPA 8260B_2_1996 S Good Standing
Pyrene EPA 625 NPW Good Standing
Pyrene EPA 8270B_(9194) NPW Good Standing
Pyrene EPA 8270B_(9194) S Good Standing
Pyrene EPA 8270C_3_1996 NPW Good Standlng
Pyrene EPA 8270C_3_1998 S Good Standing
PyrIdine EPA 625 NPW Good Standing
Pyridine EPA 8260B~_1996 NPW Good Standlng
Pyridine EPA8260B_~1996 S Good Standlng
Pyridine EPA 8270IU9194) NPW Good Standing
PyrIdine EPA 8270B_(9/94) S Good Standing
Pyridine EPA 8270C_3_1996 S Good Standing
Pyridine EPA 8270C_3_1996 NPW Good Standing
Radioactive cesium EPA 901.1 S Good Standing
Radioactive cesium EPA 901.1 NPW Good Standing
Radioactive iodine (lOdlne-131) EPA 901.1 S Good Standing
Radioactive Iodine (iodine-131) EPA 901.1 NPW Good Standing
Radium-224 EPA 9315_(9186) S Good Standlng
Redlum-224 EPA 9315_(9/86) NPW Good Standing
Radium-226 EPA 903 S Good Standlng
Radlum-226 EPA 903 NPW Good Standing
Radium-226 EPA 9315_(9188) S Good Standing
Radium-226 EPA 9315_(9186) NPW Good Standing
Radium-226 EPA 9320_(9/86) NPW Good Stanc!fng
Radium-226 EPA 9320_(9186) S Good Standing
Radlum-226 SM 18J191hEO 305 S Good StandIng
Radium-226 SM 18119thEO 305 NPW Good Standing
Radlum-228 EPA 904 NPW Good Sianding
Radlum-228 EPA 9315_(9186) S Good Sianding
Radium-228 EPA 9315_(9186) NPW Good Standing
Radlum-228 EPA 9520_(9/86) NPW Good Standing
Radium-228 EPA 9320_(9/86) S Good Standing
Reactive sulfide EPA 7.3.3.2_3_1995 NPW Good Standing
Reactlve sulfide EPA 7.3.3.2_3_1996 S GoocI Standing
Resldue-filtarable (TOS) SM 2540 C 20th ED (1998) NPW Good Standing
Resldue-nonfdterable erSS) SM 2540 0 20th ED (1998) NPW Good Standing
Residue-total SM 2540 B 20th ED (1998) NPW Good Standing
Residue-volatile EPA 160.4 NPW Good Standing
Resorcinol EPA 82708_(9/94) NPW GOOd Standinl!
Resorcinol EPA 82708_(9/94) S Good Standing
Resorcinol EPA 8270C_3_1900 S Good Standing
Resorcinol EPA 8270C_:U996 NPW Good Standing
Page 32
OKLAHOMA DEPARTMENT OF HIVIR.ONMENTAl QUAliTY
••• faT 0 clean, attrodive. prosperolJS OklDhomo
Laboratory 10: OK00922
State lab ID: 9517
Clean Water Program
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
Broken Arrow, OK 74012
(918)-251-2515
Certificate Number. 2009-105
Date of Issue: 9/112009
expiration Date: 8131/2010
Has demonstrated the capability to analyze environmental samples In accordance with Oklahoma Rules 252:301
and is hereby granted CERTIFICATION FOR:
Ssfrole
Safro!e
Sarro!.
Safro!e
Safro!e
Safrole
sec-ButylbenzBne
sec-Butylbenzene
Selenium
Selenium
Selenium
Se!enlum-75
Selenium-75
Silica as Si02
Silica as 5/02
SilicaasSi02
SIIica-dissolved
Silica-dlssolved
Sillcon
Silioon
Silver
Silver
Sliver
Sllvex (2.4,6-TP)
Sodium
Sodium
Sodium
Strontium
Strontium
Strontlum-89, 80
Strontium-90
Shychnine
Strychnine
Stlychnine
Strychnine
S1yIene
S1yIene
Styrene
Sulfallate
Sulfallllte
Sulfate
Sulfide
Su!flde
Sulnde
Synlhetic Precipitation leaching Procedure (SPlP)
EPA 82608_2_1996
EPA 82Ei08_~U996
EPA 82708_(9/94)
EPA 8270B_(9194)
EPA 8270C_3_1996
EPA 8270C_:U996
EPA 8260B_2_1996
EPA 82608_2_1996
EPA 200.7_5_1998
EPA6010B_2_1996
EPA 6010B_2_1996
EPA 901.1
EPA 901.1
EPA 200.7_5_1998
EF'A 60109_2_1996
EPA 60109_2_1996
EPA 200.7_5_1998
EPA 300.0
EPA 80109_2_1898
EPA 80109_2_1996
EPA 200.7_5_1998
EPA 60108_2_1996
EPA6010B_2_199&
EPA 8151A_(1/98)
EPA 200.7_5_1998
EPA 60109_2_1996
EPA 80108_2_1996
EPA 6010B_2_19913
EPA6010B_2_1996
EPA 905
EPA 905
EPA 8270B_(8/94)
EPA 82709_(9194)
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 624
EPA 8260B_2_1998
EPA 8280B_2_1998
EPA 8270C_3_1998
EPA 8270C_3_1998
ASTM 0516-90
EPA 378.1_1978
EPA 376.1_1978
SM 4500-$2» F 20th ED (1998)
EPA 1312_0_1994
Page 33
NPW
S
NPW
S
S
NPW
NPW
S
NPW
NPW
S
NPW
S
NPW
S
NPW
NPW
NPW
NPW
S
NPW
NPW
S
S
NPW
NPW
S
NPW
S
NPW
NPW
S
NPW
S
NPW
NFW
NFW
S
NPW
S
NPW
S
NPW
NPW
NPW
Good Standing
Good standing
Good Slanding
Good Standing
Good Standing
Good Standing
Good Standing
Good StandIng
Good Standing
Good Standing
Good Standing
Good Standing
Good Slanding
Good Standing
Good Standing
Good Slanding
Good Slanding
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good standing
Good Standing
Good Slanding
Good Standing
Good Slanding
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good standing
Good Slanding
Good Standing
Good Standing
Good Standing
Good standing
Good standing
Good Standing
Good Standing
Good Standing
Good Standing
OKLAHOMA
DEPARTMENT Of ENVIRONMENTAL QUAlITY
... for a dean, o/1Jl!cIiYe, flIOSpeRIUS OkJohomo
Laboratory ID: OK00922
state Lab 10: 9517
Clean Water Program
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
Broken Arrow, OK 74012
(918)-251-2515
Certificate Number: 2009-105
Date ofIssue: 911/2009
expiration Date: 813112010
Has demonstrated the capablllty to analyze environmental samples In accordance with Oklahoma Rules 252:301
and is hereby granted CERTIFICATION FOR:
SynthetIc Preclpita~ion Leaching Procedure (SPLP)
T -amylmelhyJether (TAME)
T -amytmethylether (TAME)
Terbufos
Terbufos
lert·Butyl alcohol
tert·Butyl alcohol
lert·Butylbenzene
lert·Butylbenzene
Tetrachloroethylene (Perchloroelhylene)
Tetrachloroethylene (Perchloroethylene)
Tetrachloroethylene (Perchloroethylene)
Tetrachlorvinphos (SUrophos. Gardona)
Tetrachlorvlnphos (Stirophos. Gardona)
Tetraethyl dlthlopyrophosphale
Tetraethyl dithiopyrophosphate
Tetraethyl pyrophosphate (TEPP)
Tetraethyl pyrophosphate (TEPP)
Thallium
Thallium
Thallium
Thionazln (Zlnophos)
Thionazin (Zinophos)
Thiophenol (Benzenethlol)
Thlophenol (Benzenethlol)
Thiophenel (Benzenethlol)
Thlophenol (Benzenethiol)
Tin
11n
Tin
11tanlum
11tanium
11tanium
Toluene
Toluene
Toluene
Toluene dllsocyanate
Toluene dlisocyanate
Toluene dllsocyanate
Toluene dlisocyanate
Total alpha Tl!d1um
Total alpha radium
Total cyanide
Total cyanide
Total organic carbon
EPA 1312_0_1994
EPA 82608_2_1996
EPA 8260B_2_199&
EPA 8270C_:U996
EPA 8270C_3_1996
EPA 8260S_2_1996
EPA 8260B_2_1996
EPA 8260B_2_199&
EPA 82&OB_2_1996
EPA 624
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82700_3_1996
EPA 82700_3_1996
EPA 82700_3_1996
EPA 82700_3_'998
EPA 82700_3_1996
EPA 82700_3_'996
EPA 200.7_5_1998
EPA 6010B_2_1S98
EPA6010B_2_1998
EPA 8270C_3_'996
EPA 92700_3_'99S
EPA 82708_(9/94)
EPA 8270B_(9/94)
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 200.7_5_199a
EPA8010B..2_'998
EPA 6010B_2_' 99S
EPA 200.7_5_'998
EPA 60108_2_1996
EPA8010B_2_'99&
EPA 824
EPA 8260B_2_1996
EPA 8280B_2_'998
EPA 8270B_(9/94)
EPA 8270B_(9/94)
EPA 8270C_3_'998
EPA 8270C_3_1996
EPA 9315_(9/86)
EPA 9315_(9188)
EPA 90'4_0_'998
SM 4500-CN E 20th ED (1998)
EPA9060A
Page 34
S
NPW
S
S
NPW
5
NPW
S
NPW
NPW
NPW
S
S
NPW
S
NPW
NPW
S
NPW
NPW
S
NPW
S
S
Npw
S
NPW
NPW
S
NPW
NPW
S
NPW
NPW
NPW
S
S
NPW
NPW
S
S
NPW
NPW
NPW
NPW
Good Slanding
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Goocl Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good S1anding
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
OKLAHOMA
DEfAR1MENT OF ENVIRONMENTAL QUAlitY
••• (Of a clean, ollmdive, prospero/lS Oklahomo
Laboratory ID: OK00922
State Lab 10: 9517
Clean Water Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
Broken Arrow, OK 74012
(918)-251-2515
Certifieate Number: 2009-105
Date of Issue; 9/112009
Expiration Oa te: 8131/2010
Has demonstrated the capability to analyze environmental samples in accordance with Oklahoma Rules 252:301
and is hereby granted CERTIFICATION FOR:
Total organic carbon
Total organie halides (TOX)
Tolal organic halides (TOX)
Total phenolics
Totel phenolics
Total radium
Totel radium
Total radium
Total radium
Toxaphene (Chlorinated camphene)
Toxaphene (Chlorinated camphene)
Toxaphene (Chlorinated camphene)
Toxaphene (Chlorinated camphene)
Toxaphene (Chlorinated camphene)
Toxicity Characteristic Leaching Procedure (TClP)
Toxicity CharacteristiC leaching Procedure (TClP)
loxlclty Characteristic leaching Procedure (TCLP)
Toxicity Characteristic Leaching Procedure (TCLp)
trans-1,2-Dlcloroethytene
trans-1.2-DicJoroethylene
trans-1 ,2-0ieloroethylene
lrans-1.3-OIchloropropylene
ltans-1.3-Dichloropropylene
tr.ms-1.3-0ichloropropylene
trans-1.4-0Ichloro-2-bulene
1rans-1,4-Oichloro-2-butene
Trichloroethene (Trichloroethylene)
Trichloroethene (Trichloroethylene)
Trichloroethene (Trichloroethylene)
Trichloroftuoromethane
Trichloroftuoromethane
Trlchloronuoromethane
Trlfturalin (Treflan)
TrifluraJin (Trenan)
Trlmethyl phosphate
Trimethyl phosphate
Trl-p-tDlyI phosphate
TrI-p-tolyi phosphate
tris-(2.3-Dibromopropy~ phosphate (Irls-BP)
lris-(2,3-Dibromopropyl) phosphate (lris-BP)
Tritium
Turbidity
Turbidity
Uranium
Uranium
SM 5310 C 20th ED (1998)
EPA 9020A_(7192)
EPA 902QA..(7192)
EPA 420.1_1978
EPA 9065_0_1986
EPA 903
EPA 903
EPA 9315_(9186)
EPA 9315_(9186)
EPA 625
EPA 8081 B_(11/00)
EPA 8081 B_(11100)
EPA 8270C_3_1996
EPA 8270C_3_199B
EPA 1311_0_1992
EPA 1311_'U992
EPA 1312_0_1994
EPA 1312_0_1994
EPA 624
EPA 8260B_2_1996
EPA 6260B_2_1996
EPA 624
EPA 8260B_2_1996
EPA 8260B_2_1996
EPA 8260B_2_1996
EPA 8260B_2_1996
EPAS24
EPA 8260B_2_1998
EPA 82608_2_1996
EPA 624
EPA 8260B_2_199S
EPA 82608_2_1996
EPA 827OC_3_1996
EPA 827OC_3_199S
EPA 8270C_3_1996
EPA 627OC_3_1996
EPA 8270C 3 1998
EPA 827OC:(1998
EPA 8270C_3_1996
EPA 8270C_3_199S
EPA 906
EPA 180.1
SM 2130 B 20th ED (1998)
ASTM D 5174-91
ASTM 0 5174-91
page 35
NPW
S
NPW
NPW
NPW
NPW
S
S
NPW
NPW
S
NPW
NPW
S
S
NPW
NPW
S
NPW
NPW
S
NPW
S
NPW
S
NPW
NPW
S
NPW
NPW
NPW
S
NPW
S
S
NPW
S
NPW
S
NPW
NPW
NPW
NPW
NPW
S
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standlng
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good SIanding
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standi JIg
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good SIancllng
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good StancJIng
Good Standing
Good Standing
Good Standing
Good Standing
OKLAHOMA
!)[PAR1MfNT Of ENVIRONMENTAL QUALITY
.•• far D cl8tm, oltToctive, pro5p8f(1US Oklahoma
Laboratory ID: OK00922
State Lab ID: 9517
Clean Water Program
Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
Broken Arrow, OK 74012
(918)-251-2515
Certificate Number: 2009-105
Date ofIssue: 9/112009
Expiration Date: 8/3112010
Has demonstrated the capability to analyze environmental samples in accordance with Oklahoma Rules 252:301
and is hereby granted CERTIFICATION FOR:
Vanadium EPA 200.7_5_1998 NPW Good Standing
Vanadium EPA6010B_2_1S9S S Good Standing
Vanadium EPA 6010B_2_1996 NPW Good Standing
Vinyl acetate EPA 8260B_2_1996 S Good Standing
Vinyl acetate EPA 6260B_2_1996 NPW Good Standing
Vinyl chloride EPA 624 NPW Good Standing
Vinyl chloride EPA 8260B..2_1996 S G'ood Standing
Vinyl chloride EPA 8260B_2_1996 NPW Goed Standing
Xenon-133 EPA901.1 NPW Good Standing
Xenon-133 EPA 901.1 S Good Standing
Xylene (total) EPA 8260B_2_1996 NPW Good Standing
Xylene (total) EPA B250B_2_1996 S Good Standing
Ytterbium-169 EPA 901.1 NPW Good Standing
Ytterbium-16S EPA901.1 S Good Standing
Zinc EPA 200.7_5_1998 NPW Good Standing
Zine EPA 5010B_2_1996 NPW Good Standing
Zine EPA6010B_2_1996 S Good Standing
ZlneSS EPA 901 NPW Good Standing
ZlneSS EPA 901 S Good Stamflng
ZIne65 EPA 901.1 NPW Good Standing
ZI"e65 EPA 901.1 S Good Standing
DW = Drinking Water; NPW:: Non-Potable Water; S = Solids
This analyte list supercedes all previously issued.
DISPLAY IN A PROMINENT POSITION Certification Officer
Page 36
Signed Affidavit
AFFIDAVIT OF JOHN H. ELLIS
I, John H. Ellis, being duly sworn according to law, depose and state as follows:
1. I am presently employed as the President for Sequoyah Fuels Corporation
("SFC") at the company's Gore, Oklahoma facility. In that capacity I am responsible for
senior project management oversight for implementation and execution of reclamation
activities at SFC's Gore facility, operation offacility equipment and systems,
implementation and oversight of decommissioning activities, and related activities
including waste management. My experience with SFC dates back to 1992 when I was
first employed at the company's Gore, Oklahoma facility. I have personal knowledge of
the raw materials used, the production processes employed, and the waste handling
procedures followed at SFC's Gore facility.
2. SFC proposes to ship to Denison's White Mesa Mill in Blanding Utah, the
following material: dewatered raffinate sludge, for processing as alternate feed materials.
All of the proposed alternate feed materials are secondary products or waste streams
produced in the conversion of uranium or the decommissioning of uranium conversion
equipment at facilities owned and operated by SFC, and containS no materials or wastes
from any other source.
3. The raffinate sludge consists of precipitated and settled soil, rock particles,
metals, and radionuclides removed from the yellowcake feed (uranium) during the
purification process at the SFC facility. No wastes from any other source are combined
with the raffmate sludge. The raffmate sludge was passed through a filter press to remove
water thus creating the dewatered raffinate sludge.
AFFIDAVIT OF JOHN H. ELLIS (continued)
4. I have reviewed and am familiar with the Utah Hazardous and Solid Waste
Regulations R315·2·10 and R315·2·1l and the Code of Federal Regulations Title 40
Section 261.31 through 33 (the "Regulations") in the form attached hereto as Exhibit A.
Based on the processing steps employed in SFC's uranium conversion facility, the
proposed alternate feed materials do not contain any of the listed wastes enumerated in
the Regulations.
5. Based on my knowledge of waste management at SFC's facilities, the
proposed alternate feed materials have not been mixed with wastes from any other source,
which may have been defined as or which may have contained listed wastes enumerated
in the Regulations.
6. Specifically, the proposed alternate feed materials do not contain
hazardous wastes from non· specific sources (Utah RCRA F type wastes) because (a)
SFC does not operate any processes which produce the types of wastes listed in Section
261.31 of Title 40 of the Regulations, and (b) SFC has never accepted, nor have the
proposed alternate feed materials ever been combined with. wastes from any other source
which contain Utah RCRA F type wastes as defined therein.
7. Specifically, the proposed alternate feed materials do not contain
hazardous wastes from specific sources (Utah. RCRA K type wastes) because SFC does
not operate any of the processes which produce the types of wastes listed in Section
261.32 of Title 40 of the Regulations, and (b) SFC has never accepted. nor have the
proposed alternate feed materials ever been combined with, wastes from any other source
which contain Utah RCRA K type wastes as defined therein.
AFFIDAVIT OF JOHN H. ELLIS (continued)
8. Specifically, the proposed alternate feed materials are not Utah RCRA P or
U type wastes as defined in Section 261.33 of Title 40 of the Regulations because they (a)
are not manufactured or fonnulated commercially pure grade chemicals, off spec
commercial chemical products or manufacturing chemical intennediates, residues from
containers that held commercial chemical products or manufacturing chemical
intermediates, or any residue or contaminated soil. water or other debris'resulting from a
spill cleanup, and (b) SFC has never accepted, nor have the proposed alternate feed
materials ever been combined with, wastes from any other source which contain Utah
RCRA P or U type wastes as defined therein.
Dated ~,J day of fiitltllMY. 2009 --#= 'XI--: JIt.;
John H. Ellls
Sworn to and subscribed before me
this~~~~ay of.j"J;,. , 2009
Notary Public
My Commission Expires:
OKLAHOMA
DEPARTMENT Of ENVIRONMENTAL QUALITY
••• for a cison, attroctive, prosperous Oklahoma
Oklahoma I)epartment of Environmental Quality
Laboratory Accreditation Program
State Laboratory ID: 9517
EPA ID: OK00922
Certificate #: 2012-004
Outreach Laboratory
311 North Aspen
Broken Arrow, OK 74012
has been certified for the examination of environmental samples for fields of testing listed on the laboratory's Scope of Accredi tation.
~ ."
Continued certification is contingent upon successful on-going compliance with OAe 252:301 which was promulgated
and adopted pursuant to the Oklahoma Environmental Quality Code (Code), 27AO.S. § 2-4-101 et seq.
Specific methods and analyteS certified are cited on the laboratorl s Scope of Accreditation.
The Scope of Accreditation and reports of on-site inspections are on file at the Oklahoma DEQ> State Environmental Laboratory
Services Division, Laboratory Accreditation Program, 707 N Robinson. P.O. Box 1677, Oklahoma City, Oklahoma 73101-1677,
[phone], www.deq..state.ok.us.Clients and customers may verify with this agency the
laboratory's certification status forparticuIar methods and analytes .
ISSUED: 9/1/2012 EXPIRES: 8/31/2013
9aJ~~~
ry Services Division Director David Caldwell, Laboratory Accreditation Program
This certificate is valid proof of certification only when associated with its Scope of Accreditation.
I ~ Oklahoma Department of Environmental Quality
Laboratory Accreditation Program
......r..-...-~T~ , -~~-. ..;;;;.;:-.... ~ 7· ;
OKLAHOMA
OEPARTMENT OF eNVIRONMENTAL QUAliTY
... for 0 clean, ottractive, prosperous Oklahoma
Laboratory 10: OK00922
State lab ID: 9517
Safe Drinking Water Program
Scope of Accreditation
Outreach Laboratory
311 North Aspen
Broken Arrow, OK 74012
[phone]
Certificate Number: 2012-004
Date of Issue: 9/112012
Expiration Date: 8/31/2013
Has demonstrated the capability to analyze environmental samples in accordance with Oklahoma Rules 252:301
and Is hereby granted CERTIFICATION FOR:
MatrixlAnalyte
Drinking Water
Natural uranium
Gross-alpha
Gross-beta
Gamma Emitters
Radium-228
Strontium-89, 90
Tritium
Radium-226
Non-Potable water
Chloride
Sulfate
Ignilabflity
Conductivity
Toxicity Characteristic Leaching Procedure (TCLP)
ToxiCity Characterlstic Leaching Procedure (TCLP)
Residue-volatile
011& Grease
Aluminum
Antimony
Arsenic
Barium
Beryllium
Boron
Cadmium
Method Status
ASTM D5174-97 Good Standing
EPA 900 Good Standing
EPA 900 Good Standing
EPA 901.1 Good Standing
EPA 904 Good Standing
EPA 905 Good Standing
EPA 906 Good Standing
SM 7500-Ra B (GPC) 19th Good Standing
ED (1995)
ASTM D512-B9A Good Standing
ASTM 0516-90 Good Standing
EPA 1010A Good Standing
EPA 120.1_1982 Good Standing
EPA 1311_0_1992 Good Standing
EPA 1312_0_1994 Good Standing
EPA 160.4 Good Standing
EPA 1664A Good Standing
EPA 200.7_4.4_1994 Good Standing
EPA 200.7_4.4_1994 Good Standing
EPA 200.7_4.4_1994 Good Standing
EPA 200.7_4.4_1994 Good Standing
EPA 200.7_4.4_1994 Good Standing
EPA 200.7_4.4_1994 Good Standing
EPA 200.7_4.4_1994 Good Standing
Notes
Oklahoma Department of Environmental Quality
Effective Date: 9/112012
Laboratory Accreditation Unit
Scope of Accreditation Report for Outreach Laboratory
2012-004
Page 1 of 16
Scope Expires: 8/31/2013
MatrixlAnalyte
Calcium
Chromium
Cobalt
Copper
Iron
Lead
Magnesium
Manganese
Molybdenum
Nickel
Phosphorus. total
Potassium
Selenium
Silica as 5i02
Silver
Sodium
Thallium
TIn
Titanium
Vanadium
Zinc
Mercury
Nitrate as N
Aluminum
Antimony
Arsenic
Barlum
Beryllium
Bismuth
Boron
Cadmium
Calcium
Chromium
Chromium VI
Cobalt
Copper
Iron
Lead
Uthlum
Magnesium
Manganese
Molybdenum
Nickel
Oklahoma Department of Environmental Quality
Effective Date: 9/1/2012
Scope of Accreditation Report for Outreach Laboratory
2012-004
Outreach Laboratory
Method
EPA 200.7_4.4_1994
EPA 200.7_4.4_1994
EPA 200.7_4.4_1994
EPA 200.7_4.4_1994
EPA 200.7_4.4_1994
EPA 200.7_4.4_1994
EPA 200.7_4.4_1994
EPA 200.7_4.4_1994
EPA 200.7_4.4_1994
EPA 200.7_4.4_1994
EPA 200.7_4.4_1994
EPA 200.7_4.4_1994
EPA 200.7_4.4_1994
EPA 200.7_4.4_1994
EPA 200.7_4.4_1994
EPA 200.7_4.4_1994
EPA 200.7_4.4_1994
EPA 200.7_4.4_1994
EPA 200.7_4.4_1994
EPA 200.7 _4.4_1994
EPA 200.7_4.4_1994
EPA 245.1_3_1994
EPA 352.1_1971
EPA 6010B_2_1996
EPA 6010B_2_1996
EPA 60108_2_1996
EPA 601 DB _2_1996
EPA 6010B_2_1996
EPA 60108_2_1996
EPA 60108_2_1996
EPA 6010B_2_1996
EPA 6010B_2_1996
EPA 6010B_2_1996
EPA 60108_2_1996
EPA 60108_2_1996
EPA 60108_2_1996
EPA6010B_2_1996
EPA 6010B_2_1996
EPA 601 OB_2_1996
EPA 6010B_2_1996
EPA 6010B_2_1996
EPA 60108_2_1996
EPA 60108_2_1996
Status Notes
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
laboratory Accreditation Unit
Page 2 of 16
Scope expires: 8/31/2013
I .
MatrixlAnalyte
Phosphorus. total
Potassium
Selenium
Silica as Si02
Silicon
Silver
Sodium
Strontium
Thallium
Tin
Titanium
Vanadium
Zinc
4,4'·DOO
4,4'·DDE
4,4'·DDT
Aldrin
alpha·SHC (alpha·Hexachlorocyclohexane)
Aroclor-1016 (PCB-1016)
Aroclor-1221 (PCS-1221)
Aroclor-1232 (PCS·1232)
Aroclor-1242 (PCS-1242)
Aroclor-124B (PCS·124B)
Aroclor-1254 (PCB-1254)
Aroclor-1260 (PCB-i2S0)
beta·SHC (beta· Hexachlorocyclohexane )
Chlordane (tech.)
delta·SHC
Dieldrin
Endosulfan I
Endosulfan II
Endosulfan sulfate
Endrin
Endrln aldehyde
Endrln ketone
gamma·SHC (Lindane, gamma·HexachlorocyclohexanE)
Heptachlor
Heptachlor epoxide
Meihoxychlor
Toxaphene (Chlorinated camphene)
1,1,1-Trichloroethane
1,1 ,2,2-Tetrachloroethane
1,1,2-Trichloroethane
Oklahoma Department of Environmental Quality
Effective Date: 9/1/2012
Scope of Accreditation Report for Outreach Laboratory
2012-004
Outreach Laboratory
EPA 60108_2_1996
EPA 60106_2_1996
EPA 60108_2_1996
EPA 60108_2_1996
EPA 60106_2_1996
EPA 60108_2_199S
EPA6010B_2_1996
EPA 60108_2_1996
EPA 60106_2_1996
EPA 60108_2_1996
EPA 60108_2_1996
EPA6010B_2_1996
EPA 60108_2_1996
EPA 608
EPA60B
EPA 608
EPASOS
EPASOS
EPA 608
EPA 608
EPA 608
EPA SOB
EPA 608
EPA 608
EPA 608
EPA 60S
EPA 608
EPA 608
EPASOS
EPA 60S
EPASOS
EPA 608
EPASOS
EPA 60S
EPAS08
EPA 608
EPA 60S
EPA 608
EPA 608
EPA 608
EPA 624
EPA 624
EPA 624
Status Notes
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Sianding
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Laboratory Accreditation Unit
Page 3 of 16
Scope Expires: 8/31/2013
MatrixiAnalyte
1,1-Dichloroethane
1,1-Dichloroethylene
1,2-Dichlorobenzene
1,2-Dichloroethane
1,2-Dichloropropane
1,3-Dichlorobenzene
1,4-Dichlorobenzene
2-Chloroethyl vinyl ether
Acrolein (Propene I)
Acrylonitrile
Benzene
Bromodichloromethane
Bromoform
Carbon tetrachloride
Chlorobenzene
Chloroethane
Chloroform
cis-1,3-0ichloropropene
Dibromochloromethane
Dichlorodlfluoromethane
Ethylbenzene
Methyl bromide (Bromomethane)
Methyl chloride (Chloromethane)
Tetrachloroethylene (Perchloroethylene)
Toluene
trans-1,2-Dicloroethylene
trans-1 ,3-Dichloropropylene
Trichloroethene (Trichloroethylene)
Trichlorofluoromethane
Vinyl chloride
1,2,4-Trich lorobenzene
1,2-0ichlorobenzene
1,3-0lchlorobenzen e
1,4-Dichlorobenzene
2,3-Dinltrophenol
2,4,5-Trichlorophenol
2,4,6-Trichlorophenol
2,4-Dich lorophenol
2,4-Dimethylphencl
2,4-Dinitrophenol
2,4-0initrotoluene (2,4-DNT)
2,6-0initrotoluene (2,6-DNT)
2-Chloronaphthalene
Oklahoma Department of Environmental Quality
Effective Date: 9/1/2012
Scope of Accreditation Report for Outreach Laboratory
2012-004
Outreach Laboratory
Method
EPA 624
EPA 624
EPA 624
EPA 624
EPA 624
EPA 624
EPA 624
EPA 624
EPA 624
EPA 624
EPA 624
EPA 624
EPA 624
EPA 624
EPA 624
EPA 624
EPA 624
EPA 624
EPA 624
EPA 624
EPA 624
EPA 624
EPA 624
EPA 624
EPA 624
EPA 624
EPA 624
EPA 624
EPA 624
EPA~24
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
Status Notes
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Laboratory Accreditation Unit
Page 4 of 16
Scope Expires: 8/31/2013
MatrixlAnalyte
2-Chlorophenol
2-Methyl-4,6-dinitrophenol
2-Nitrophenol
3,3'-Oichlorobenzidine
4,4'-DDD
4,4'-DDE
4,4'-DDT
4-Bromophenyl phenyl ether
4-Chloro-3-methylphenol
4-Chlorophenyl phenyJether
4-Nitrophenol
Acenaphthene
Acenaphthylene
Aldrin
alpha-BHC (alpha-Hexachlorocyclohexane)
Anthracene
Aroclor-1016 (PCB-1016)
Aroclor-1221 (PCB-1221)
Aroclor-1232 (PCB-1232)
Aroclor-1242 (PCB-1242)
Aroclor-1248 (PCB-1248)
Aroclor-1254 (PCB-12S4)
Aroclor-1260 (PCB-1260)
Benzidine
Benzo(a)anthracene
Benzo(a)pyrene
Benzo(g,h,l)perylene
Benzo(k)nuoranthene
Benzolbjfluoranthene
beta-BHC (bela-Hexachlorocyclohexane)
bis(2-Chloroethoxy)methane
bis(2-Chloroethyl) ether
bis(2-Chloroisopropyl) ether
bis(2-Ethylhexyl) phthalate (DEHP)
Butyl benzyl phthalate
Chlordane (tech.)
Chrysene
delta-SHC
Dibenz(a,h) anthracene
Dieldrin
Oiethyl phthalate
Dimethyl phthalate
Di-n-butyl phthalate
Oklahoma Department of Environmental Quality
Effective Date: 9/1f2012
Scope of Accreditation Report for Outreach Laboratory
2012-004
Outreach Laboratory
Method
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPAS25
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
Status Notes
Good Standing
Good Standing
Good .Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Laboratory Accreditation Unit
Page 5 of 16
Scope Expires: 8/31/2013
Matrix/Analyte
Oi-n-octyl phthalate
Endosulfan I
Endosulfan II
Endosulfan sulfate
Endrin
Endrin aldehyde
Fluoranthene
Fluorene
gamma-BHC (Lindane, gamma-HexachlorocyclohexanE)
Heptachlor
Heptachlor epoxide
Hexachlorobenzene
Hexachlorobutadiene
Hexachlorocyclopentadiene
Hexachloroethane
Indeno(1,2,3-cd) pyrene
lsophorone
Naphthalene
Nitrobenzene
n-Nitrosodlmelhylamine
n-Nitrosodi-n-propylamine
n-Nitrosodiphenylamine
Pentachlorophenol
Phenanthrene
Phenol
Pyrene
Toxaphene (Chlorinated camphene)
Chromium VI
Mercury
Mercury
2,4'-ODO
2,4'-ODE
2,4'-ODT
4,4'-ODD
4,4'-ODE
Aldrin
alpha-BHC (alpha-Hexachlorocyclohexane)
alpha-Chlordane
beta-SHe (beta-Hexachiorocyciohexane)
Chlordane (tech.)
delta-SHC
Dieldrin
Endosulfan I
Oklahoma Department of Environmental Quality
Effective Date: 9/1/2012
Scope of Accreditation Report for Outreach Laboratory
2012-004
Outreach Laboratory
Method
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 625
EPA 7196A_1_1992
EPA 7470A...1_1994
EPA 7471A_1_1994
EPA 8081B_(11/oo)
EPA 8081 B_(11100)
EPA 8081B_(11/00)
EPA 80818_(11100)
EPA 80818_(11/00)
EPA 8081 B_(11/00)
EPA 8081 B_(11/00)
EPA 8081 B_(11/00)
EPA 80818_(11/00)
EPA 80818_(11100)
EPA 8081B_(11/00)
EPA 8081B_(11/00)
EPA 8081B_(11/00)
Status Notes
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Sianding
Good Standing
Good Standing
Good Stending
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good StandIng
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Laboratory Accreditation Unit
Page 6 of 16
Scope Expires: 8/31/2013
MatrixlAnalyte
Endosulfan II
Endosulfan sulfate
Endnn
Endrin aldehyde
Endrin ketone
gamma-SHC (Lindane, gamma-HexachlorocyclohexanE)
gamma-Chlordane
Heptachlor
Heptachlor epoxide
HexachJorobenzene
Methoxychlor
Toxaphene (Chlorinated camphene)
Aroclor 1268 (PCB-126S)
Aroclor-1016 (PCB-1016)
Aroclor-1221 (PCB-1221)
Aroclor-1232 (PCB-1232)
Aroclor-1242 (PCB-1242)
Aroclor-1248 (PCB-1248)
Aroclor·1254 (PCB-1254)
Aroclor-1260 (PCB-1260)
Aroclor-1262 {PCB-1262}
2.4,5-T
2,4-0
2,4--DB
3,5-Dichlorobenzoic acid
4-Nitrophenol
Acifluorfen
Bantazon
Bromlnal (Bromoxynil)
Chloramben
Dacthal (DCPA)
Dalapon
Dlcamba
Dichloroprop (Dichlorprop)
Dlnoseb (2-sec-butyJ-4,6-dJnitrophenol, DNBP)
MCPA
MCPP
Silvex (2.4,5-TP)
1,1,1,2-Tetrachloroethane
1,1,1-Trichloro-2-propanone
1,1 ,i-Trichloroethane
1,1,2,2-Tetrachloroethane
1,1,2-Trichloro-1,2.2-trifluoroethane
Oklahoma Department of Environmental Quality
Effective Date: 9/1/2012
Scope of Accreditation Report for Outreach Laboratory
2012-004
Outreach Laboratory
Method
EPA 80818_(11/00)
EPA 8081B_(11/00)
EPA 80818_(11/00)
EPA 8081 B_(11/00)
EPA 80818_(11/00)
EPA 80818_(11/00)
EPA 8081 B_(11/00)
EPA 8081B_(11/00)
EPA 80816_(11/00)
EPA 80818_(11/00)
EPA 8081 B_(11/00)
EPA 8081 B_(11/00)
EPA 8082_o_1996
EPA 8082_0_1996
EPA 8082_0_1996
EPA 8082_0_1996
EPA 8082_0_1996
EPA 8082_0_1996
EPA 8082_0_1996
EPA 8082_0_1996
EPA 8082_0_1996
EPA 8151A_(1/98)
EPA 8151A_{1J98)
EPA 8151A_(1I98}
EPA 8151~(1/98)
EPA 8151A_(1/98)
EPA 8151A_(1/98)
EPA 8151A_{1I98)
EPA 8151A_(1/98)
EPA 8151A_(1/98)
EPA 8151A_(1/98)
EPA 8151A_(1I98)
EPA 8151A_{1I98)
EPA 8151A_(1/98)
EPA 8151A_(1/98)
EPA 8151A_(1/98)
EPA 8151A_(1/98)
EPA 8151A_(1/98)
EPA 8260B_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
Status ~IA"' __
•• "' ..... .i:J
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
GQod Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Laboratory Accreditation Unit
Page 7 of 16
Scope Expires: 8/31/2013
MatrixiAnalyte
i ,i ,2-Trichioroethane
1,1,2-Trichlorofluoroethane
1,1-Dlchloroethane
1,1-Dichloroethylene
1,1-Dichloropropene
1,2,3-Tnchlorobenzene
1,2,3-Trichloropropane
1,2,4-Trichlorobenzene
1,2,4-Trimethylbenzene
1,2-Dibromo-3-chloropropane (DBCP)
1,2-Dibromoethane (ED8, Ethylene dibromide)
1,2-Dichloro-1,1,2,2-tetrafluoroethane
1,2-Dichloro-1-1-2-trifluoroethane
1,2-Dichlorobenzena
1,2-Dichloroethane
1,2-Dichloropropane
1,3,5-Trichlorobenzene
1,3,5-Trimethylbenzene
1,3-Dlchlorobenzene
1,3-Dichloropropane
1,3-Dichloropropene
1 A-Dichlorobenzene
1,4-Dioxane (1,4-Diethyleneoxlde)
1,4-lsopropyltoluene
1-Methylnaphthalene
2,2-0ichloropropane
2-Butanone (Methyl ethyl ketone, MEK)
2-Chloro-1,3-butadiene (Chloroprene)
2-Chloroethyl vinyl ether
2-Chlorotoluene
2-Hexanone
2-Methylnaphthalene
2-Nitropropane
2-Pentanone
2-Picollne (2-Methylpyridlne)
4-Bromofluorobenzene
4-Chlorotoluene
4-Methyl-2-pentanone (MIBK)
Acetone
Acetonitrile
Acrolein (Propanal)
Acrylonitrile
Benzene
Oklahoma Department of Environmental Quality
Effective Date: 9/1/2012
Scope of Accreditation Report for Outreach Laboratory
2012-004
Outreach Laboratory
Method
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 8260B_2_1996
EPA 8260B_2_1996
EPA 8260B_2_1996
EPA 8260B_2_1996
EPA 8260B_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 8260B_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 8260B_2_1996
EPA 82608J_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 8260B_2_1996
EPA 8260B_2_1996
EPA 82608_2_1996
EPA 8260B_2_1996
EPA 8260B_2_1996
EPA 82608_2_1996
EPA 8260B_2_1996
EPA 8260B_2_1996
EPA 82608_2_1996
EPA 82606_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 8260B_2_1996
EPA 8260B_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 8260B_2_1996
EPA 8260B_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
Statu $ Notes
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Sianding
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Goed Standing
Laboratory Accreditation Unit
Page 8 of 16
Scope Expires: 8/3112013
MatrixlAnalyte
Benzyl alcohoi
bis(2-Chloroisopropyl) ether
bls(Chloromethyl) ether
8romobenzene
Bromochloromethane
Bromodichloromethane
Bromoethane (Ethyl Bromide)
Bromoform
Carbon disulfide
Carbon tetrachloride
Chlorobenzene
Chloroethane
Chloroform
Chloromethyl methyl ether
cis & trans-1,2-Dichloroethene
cls-1,2-Dlchloroethylene
cls-1,3-Dlchloropropene
Cyclohexane
Dlbromochloromethane
Dibromochloropropane
Dibromofluoromethane
Dibromomethane
Dichlorodifluoromethane
Dichtorofluoromethane
Dicyclopentadiene
DiethyJ ether
Diethylamine
Diethylene glycol
DI-isopropylether (DIPE)
Ethyl acetate
Ethyl chloride
Ethylbenzene
Ethylene dichloride
Ethylene glycol
Ethyl·t-Dulylether (ETBE)
Heptane
Hexachlorobutadiene
Hexachloroethane
Hexane
Isopropyl ether
lsopropylbenzene
Methyl bromide (Bromomethane)
Methyl chloride (Chloromethane)
Oklahoma Department of Environmental Quality
Effective Date: 9/1/2012
Scope of Accreditation Report for Outreach laboratory
2012·004
Outreach Laboratory
Method
EPA 8260B_2_1996
EPA 8260B_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82608J._1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 8260B_2_1996
EPA 8260B_2_1996
EPA 8260B_2_1996
EPA 8260B_2_1996
EPA 82608_2_1996
EPA 8260B_2_1996
EPA 8260B_2_1996
EPA 82606_2_1996
EPA 82608_2_1996
EPA 8260B_2_1996
EPA 8260B_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 8260B_2.:1996
EPA 8260B_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 8260B_2_1996
EPA 8260B_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 8260B_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82608_2_1995
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
Status Notes
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Laboratory Accreditation Unit
Page 9 of 16
Scope Expires: 8f31/2013
MatrixiAnalyte
Methyl isobutyll<etone (Hexone)
Methyl tert-butyl ether (MTBE)
Methylene bromide
m-Xylene
Naphthalene
n-Butyl alcohol
n-Butyl-acetate
n-Sutylbenzene
n-Heptane
n-Hexane
Nitrobenzene
n-Nitroso-di-n-butytamine
n-Propylamine
n-Propylbenzene
o-Xylene
p-Dloxane
p-Xylene
Pyridine
Styrene
tert-Butyl alcohol
tert-Butylbenzene
Tetrachloroethylene (Perchloroethylene)
Toluene
trans-1,2-Dicloroethylene
Trichloroethene (Trichloroethylene)
Trichlorofluoromethane
Trichlorotrifluoroethane
Vinyl acetate
Vinyl chloride
Xylene (total)
1,2,4-Trichlorobenzene
1,2-Dlchlorobenzene
1,3,5-Trichlorobenzene
1,3-Dlchlorobenzene
1 A-Dichlorobenzene
1 A-Dioxane (1,4-Diethyleneoxide)
1-Chloronaphthalene
1-Naphthylamine
2,2-oxybls (1-chloropropane)
2,3,4-Trichlorophenol
2,3,5,6-Tetrachlorophenol
2,3,5-trichlorophenol
2.4,5-Trichlorophenol
Oklahoma Department of Environmental Quality
Effectrve Date: 9/1/2012
Scope of AccredItation Report for Outreach Laboratory
2012-004
Outreach Laboratory
Method
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 8260B~2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 8260B_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 8260B_2_1996
EPA 82608_2_1996
EPA 8260B 2 1996 --.
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 8260B_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 82608_2_1996
EPA 8260B-.2_1996
EPA 8260B_2_1996
EPA 8260B_2_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 3270C_3_1996
EPA 8270C_3_1996
EPA 8270C_a_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
Status Notes
Good Standing
Good Standing
Good StandIng
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Laboratory Accreditation Unit
Page 100f 16
Scope Expires: 8/31/2013
MatrlxlAnalyte
2.4,6-Tiichlorophenol
2,4-Dlchlorophenol
2,4-Dimethylphenol
2,4-Dinitrophenol
2,4-Dinitrotoluene (2,4-DNT)
2,6-Dichlorophenol
2,6-Dlnitrotoluene (2,5-DNT)
2-Chloroanlline
2-Chloronaphthalene
2-Chlorophenol
2-Fluorobiphenyl
2-Methyl-4,6-dinitrophenol
2-Methyl-4-Chlorophenol
2-Methylnaphthalene
2-Methylphenol (o-Cresol)
2-Naphthylamine
2-Nitroaniline
2-Nitrophenol
2-Nitrotoluene
. 2-Plcoline (2-Methylpyridine)
3 & 4 Methylphenol
3,3'-Dlchlorobenzidine
3-Chloroaniline
3-Chlorophenol
3-Methylphenol (m-Crasol)
3-Nitroaniline
3-Nitrotoluene
4,4'-Methylenebis(2-chloroaniline)
4,6-Dinilro-2-methyJphenol
4-Bromophenyl phenyl ether
4-Chloro-3-methylphenol
4-Chloroaniline
4-Chlorophenol
4·Chlorophenyl phenylether
4-Methylphenol (p-Cresol)
4-Nitroaniline
4-Nitrophenol
4·Nltrotoluene
Acenaphthene
Acenaphthylene
Aniline
Anthracene
Azobenzene
Oklahoma Department of Environmental Quality
Effective Date: 9/1/2012
Scope of Accreditation Report for Outreach Laboratory
2012-004
Outreach Laboratory
Method
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1998
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_199S
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_199S
EPA 8270C_3_1996
EPA a270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_199S
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_199S
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA a270C_3_199S
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
Status Notes
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Laboratory Accreditation Unit
Page 11 of 16
Scope Expires: 8/31/2013
MatrixiAnalyte
Benzal chloride
Benzaldehyde
BenzIdine
Benzo(a)anthracene
8enzo(a)pyrene
Benzo(g,h,l)perylene
Benzo(k)f1uoranthene
Benzo[b]fluoranthena
Benzofluoranthene
BenzoIc acid
Benzyl alcohol
Benzyl chloride
bls(2-Chloroethoxy)methane
bis(2-Chloroethyl) ether
bis(2-Chloroethyloxymethane)
bis(2-Chlorolsopropyl) ether
Butyl benzyl phthalate
Chrysene
Cresols (total)
Di(2-ethylhexyl)adipate
Dibenz(a,h) anthracene
Dlphenyl ether
Diphenylamine
Fluoranthene
Ruorene
Hexachlorobenzene
Hexachlorobutadiene
Hexachlorocyclopentadiene
Hexachloroethane
Indene
Indeno(1 ,2,3-cd) pyrene
Naphthalene
n-Decane
Nitrobenzene
n-Nltrosodiethylamine
n-Nitrosodimethylamlne
n-Nitrosodi-n-propylamine
n-Nitrosodlphenylamine
n-Nitrosodipropylamine
n-Nitrosomethylethalamine
n-Octadecane
Pentachlorophenol
Phenanthrene
Oklahoma Department of Environmental Quality
Effective Date: 9/1/2012
Scope of Accreditation Report for Outreach Laboratory
2012-004
Outreach Laboratory
Method
EPA 8270C_3_1996
EPA a270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 827DC_3_1996
EPA 8270C_3_1996
EPA a270C_3_1996
EPA 8270C_3_1996
EPA 8Z7DC_3_1996
EPA B270C_3_1996
EPA 8270C_3_1996
EPA 827DC_3_1996
EPA 827DC_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 827DC_3_1996
EPA 827DC_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 827DC_3_1996
EPA 827DC_3_1996
EPA 8270C_3_1996
EPA a27DC_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_ 1996
EPA 8270C_3_1996
EPA a27De_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
Status Notes
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Sian ding
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Sianding
Good Slanding
Good Standing
Good StandIng
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Slanding
Good Standing
Good Standing
Laboratory Accreditation Unit
Page 12 of 16
Scope Expires: 8/31/2013
MatrlxlAnalyte
Phenol
pyrene
Pyridine
Gross-alpha
Gross-beta
Amenable cyanide
Total cyanide
Amenable cyanide
Total cyanide
Radium-228
pH
Corrosivity
Total organic carbon
Free liquid
Nitrate as N
Gross-alpha
Gross-beta
Radium-228
Chemical oxygen demand
Acidity, as CaC03
Alkalinity as CaC03
Hardness
Conductivity
Residue-total
Residue-filterable (TOS)
Residue-nonfilterable (TSS)
Temperature, deg. C
Chromium VI
Chloride
Chlorine
Free chlorine
Total cyanide
Total cyanide
Amenable cyanide
Fluoride
Fluoride
pH
Oklahoma Department of Environmental Quality
Effective Date: 911/2012
Scope of Accreditation Report for Outreach Laboratory
2012-004
Outreach Laboratory
Method
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 8270C_3_1996
EPA 900
EPA 900
EPA S01DC
EPA9010C
EPA 9014_o_1996
EPA 9014_0_1996
EPA9D4
EPA 9040B_2_1995
EPA 9040C
EPA 9060A
EPA9095B
EPA 9210A_(1/9B)
EPA 9310_(9/86)
EPA 9310_(9/86)
EPA 9320_(9/86)
OTHER HACH 8000
8M 2310 B 20th ED (1998)
8M 2320 B 20th ED (1998)
8M 2340 C 20th ED (1998)
SM 2510 B 20th ED (1998)
SM 2540 B 20th ED (1998)
8M 2540 C 20th ED (1998)
8M 2540 0 20th ED (1998)
SM 2550 B 20th ED (1998)
8M 3500-Cr B 20th EO
(1998)
SM 4500-CI C 20th ED
(1998)
8M 4500-C1 G 20th ED
(1998)
8M 4500-CI G 20th ED
(1998)
8M 4500-CN C 20th ED
(1998)
8M 4500-CN E 20th ED
(1998)
SM 4500-CN G 20th ED
(1998)
8M 4S00-F» B 20th ED
(1998)
SM 4S00-F» C 20th ED
(1998)
SM 4500·H+ B 20th ED
Status Notes
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Laboratory Accreditation Unit
Page 13 of 16
Scope Expires: 8/31/2013
MatrixlAnalyte
Ammonia as N
Ammonia asN
Nitrite as N
Nitrate as N
Kjeldahl nitrogen -total
Oxygen, dissolved
Phosphorus, total
Orthophosphate as P
Phosphorus, total
Sulfide
Silica as Si02
Sulfite-S03
Biochemical oxygen demand
Carbonaceous BOD, CBOD
Chemical oxygen demand
Total organic carbon
Total radium
Solids
Ignltability
Toxicity Characteristic Leaching Procedure (TClP)
Toxicity Characteristic Leaching Procedure (TClP)
Aluminum
Antimony
ArsenIc
Barium
Beryllium
Bismuth
Boron
Cadmium
Calcium
Chromium
Chromium VI
Cobalt
Copper
Oklahoma Department of Environmental Quality
Effective Date: 911/2012
Scope of AccredItation Report for Outreach Laboratory
2012-004
Outreach Laboratory
Method
(1998)
SM 4500-NH3 B 20th EO
(1998)
8M 4500-NH3 0 20th EO
(1998)
SM 45QO-N02» 8 20th ED
(1998)
SM 4500-N03» D 20th ED
(199S)
SM 4500-Norg C 20th ED
(1998)
SM 4500-0 G 20th ED (1998)
SM 4500-P B 5 20th ED
(1998)
SM 4500-P E 20th ED (1998)
SM 4500-P E 20th ED (1998)
SM 4500-52» F 20th ED
(1998)
SM 4500-Si02 C 20th ED
(1998)
SM 4500-S03» B 20th ED
(1998)
SM 5210 B 20th ED (1998)
SM 5210 B 20th ED (1998)
8M 5220 D 20th ED (1998)
SM 5310 C 20th ED (1998)
SM 7S00-Ra B (GPC) 19th
ED (1995)
EPA 1D10A
EPA 1311_0_1992
EPA 1312_0_1994
EPA 6010B_2_1996
EPA 6010B_2_1996
EPA 6010B_2_1996
EPA 6010BY_1996
EPA 60108_2_1996
EPA 60108_2_1996
EPA 601 OB_2_1996
EPA 60108_2_1996
EPA 6010B_2_1996
EPA 6010B_2_1996
EPA 6010B_2_1996
EPA 6010B_2_1996
EPA 60108_2_1996
Status
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Goad Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good StandIng
Good Standing
Good Standing
Good Standing
Notes
Laboratory Accreditation Unit
Page 14 of 16
Scope Expires: 8/31/2013
MatrixlAnalyte
iron
Lead
Lithium
Magnesium
Manganese
Molybdenum
Nickel
Potassium·
Selenium
Silica as Si02
Silicon
Sliver
Sodium
Strontium
Thallium
Tin
Titanium
Vanadium
Zinc
Chromium VI
Amenable cyanide
Total cyanide
Amenable cyanide
Total cyanide
Corroslvity
pH
Total organic carbon
Free liquid
Gross-alpha
Gross-beta
Radium-228
Acidity, as CaC03
Alkalinity as CaC03
Residue-total
Chloride
Total cyanide
Total cyanide
Amenable cyanide
Total radium
Oklahoma Department of Environmental Quality
Effective Date: 911/2012
Scope of Accreditation Report for Outreach Laboratory
2012-004
Outreach Laboratory
Method
EPA 60108_2_1996
EPA 6010B_2_1996
EPA 601 OB_2_1996
EPA 6010B_2_1996
EPA 60108_2_1996
EPA 60108_2_1996
EPA 60108_2_1996
EPA 60108_2_1996
EPA 6010B_2_1996
EPA 60108_2_1996
EPA 6010B_2_1996
EPA 60108_2_1996
EPA 6010B_2_1996
EPA 60106_2_1996
EPA 601DBJ_1996
EPA 60108_2_1996
EPA 60108_2_1996
EPA 6010B_2_1996
EPA 6010B_2_1996
EPA 7196~1_1992
EPA 90iDC
EPA90i0C
EPA 9014_0_1996
EPA 9014_0_1996
EPA9045D
EPA9045D
EPA 9060A
EPA 90958
EPA 9310_(9/86)
EPA 9310_{9/86)
EPA 9320_(9/86)
SM 2310 B 20th ED (1998)
SM 2320 B 20th ED (1998)
8M 2540 B 20th ED (1998)
SM 4S00-CI C 20th ED
(1998)
SM 4500-CN C 20th ED
(1998)
SM 4500-CN E 20th ED
(1998)
SM 4500-CN G 20th ED
(1998)
SM 7500-Ra B (GPC) 19th
ED (1995)
Status Notes
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good StandIng
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good StandIng
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Good Standing
Laboratory Accreditation Unit
Page 15 of 16
Scope Expires: 8/31/2013
MatrixlAnalyte
Accredited Parameter Note Detail
Authentication Signature
Oklahoma Department of Environmental Quality
Effective Date: 9/112012
Scope of Accreditation Report for Outreach Laboratory
2012·004
Outreach Laboratory
Method Status Notes
10119/2012
Date
Laboratory Accreditation Unit
Page 160f 16
Scope Expires: 8/31/2013
State of New Jersey
Department of Environmental Protection
Certifies That
Outreach £a6oratory
Laboratory Certification r D # OKOO 1
is hereby approved as a
Nationally Accredited Environmental Laboratory
to perfor,m the' analyses as indicated on qte Annual Certified Parameter List
which must accompany this, certificate to be valid
having duly met the requirements of the
Regulations Governing The Certification Of
Laboratories And Environmental Measurements N.J.A.C. 7:18 et. seq.
and
having been found compliant with the 2909 TN! Standard approved by the
'The NELAClnstitute
I
Expiration Date June 30,2013
NJDEP is a NELAP Recognized Accreditation Body
Joseph F. Aiello, Manager
Office of Quality Assurance
This certificate is to be conspicuously displayed at the laboratory with the annual certified parameter list in a location on the premises visible to the public.
Consumers are urged to verify the laboratory's current accreditation status with the State of NJ, NELAP.
New Jersey Department of Environmental Protection
National Environmental Labol'atory Accreditation Program
ANNUAL CERTIFIED PARAMETER LIST AND CURRENT STATUS
Effective as of 07/0112012 until 06/3012013
Laboratory Name: OUTREACH LABORATORY Laboratory Number: OKOOI Activity ID: NLC120001
311 N ASPEN
BROKEN ARROW, OK 74012
Cntegory: SDW07 -Rncllocbem.: Rndionctivity / Radionucllde
Eligible to
Report
Statns NJ Ditta State Code Matrix
Certified Yes NJ S DW07.0 1000 OW
Certified Yes NJ SDW07.01001 OW
Applied No NJ SOW07.02000 OW
Certified Yes NJ SOW07.03000 OW
Celtified Yes NJ SOW07.03100 OW
Certified Yes NJ SDW07.03900 DW
Certified Yes NJ SOW07.04100 OW
Certified Yes NJ SDW07.05000 OW
Applied No NJ SDW07,06000 DW
Celtitied Yes NJ SOW07.06010 OW
Certified Yes NJ SDW07.07000 DW
Cel1ified Yes NJ SDW07.08200 DW
Applied No NJ SDW07.08300 OW
Category: SDW08 -Radon in Drinking Water
Eligible to
Report
Stntus NJ Data State Code Matrix
Certified Yes NJ SDWOS.OIOOO DW
Clltegory: SHW02 -Characteristics of Hazardous Waste
Eligible to
Report
Status NJ Data State Code
Certified Yes NJ SHW02.06950
Category: SHW04 -Inorganic Pilrameters
Eligible to
Report
Stntus NJ Data State Code
Certified Yes NJ SHW04.0 1500
Mlltrix
NPW
Mlltrix
NPW
Technique Description Approved Method
Pl'Oportional or Scintillation [EPA 900.0J
48-Hour Rapid Gross Alpha Test [OTHER ECLS-R-GAl
Radiochemical [EPA902.0l
Gamma Spectromehy -Radiochemistry [EPA 901.0)
Gamma Spectrometry [EPA 901.1]
Radiochemical [SM 7500-Ra B}
Precipitation [EPA 904.0]
Precipitation [8M 7500 -Ra B]
Total Sr & Strontium 90 [EPA 905.0]
Strontium 90 [EPA90S.0}
OiSlillationlLiquid Scintillation [EPA 906.0J
Laser Phosphorimetry [ASTM 05174]
Alpha Spectrometry [ASTM 0 3972]
Technique DesCription Approved Method
Liquid Scintillation [SM 7500-Rn]
Tcchnlque J)'cscrlptioll Ap.provcd Method
TCLP, Toxicity Procedure, Shaker [SW-S461311J
T~Hlqu() Description Approvell Metll041
Acid Digestion/Aqueous Samples, Iep, FLAA [SW-84630IM]
KEY: AE = Air and Emissions, BT = Biological Tissues, DW = Drinking Water, NPW = Non-Potable Water, SCM = Solid and Chemicnl Matelials
-Annulll Certified Paramelers List --Effective as of 07101/2012 until 06/30/2013
~O~"O/f'/) ~eJ; ,~~,
~'tl·,9
Parameter Dcseription
GroSs -alpha-bela
GroSs -alpha (incl. Ra & U excl. radon)
R.1dioactive iodine
Cesii.nn 134/137
Gamma emitters
Rarlium -226
Radium-228
Radium -total
Strontium -89, 90
Stron! iutn -90
Tlitium
Urnnium
Uranium
Parameter Description
Radon
l'arn.ll:\eter Desa-iption
S~mi'Volatileorgal1ics
P~rametcr Des~riptlon
Met2~'l, Total
Paee I of Il L
New Jersey Department of Environmental Protection
National EnvironmentalLaborntory Acereditation Program
ANNUAL CERTiFIED PARAMETER LIST AND CURRENT STATUS
Effccllvl' ns of 07/0112012 until 06/30/2013
Laboratory N allle: OUTREACH LABORATORY Laboratory Number: OKOOI Activity ID: NLC120001
311 N ASPEN
BROKEN ARROW, OK 74012
Category: SHW04 -Inorganic Parameters
Eligible tf!
Report
StahlS NJ On/a Stnte Code Matrix Tccllllique DC:ttripliDn Appl'oved Method
Certified Yes NJ SHW0421000 NPW ColorimetJic [SW-S467196A]
Certified Yes NJ SHW04.33000 NPW AA, Maooal Cold Vapor [SW-S467470A]
Cfttegm1': SHWOS -Organic Parameters, Prep. J Screening
Eligible to
Report
Stntus NJ Data State Code Matrix TccluJigue Description Approved Metlilld
Certifi,~ Yes NJ SHW05.01000 NPW Separatoty Funnel Extraction [SW·8463510C]
Certifi.:d Yes NJ 5HW05.07oo0 NPW Purge & '['rep Aqueous [SW-846 5030B]
Category: SlffW06 -Orgauie Pnrametcl's, Chromatography
Eligible to
Report
Status NJ Dnta State Code Matrix Tecbnlqllc Description Approved MetllOd
Applied No NJ SHW06.12010 NPW GC, Extraction, ECD or HECD, CapillalY' [SW-846 SOSIA]
Applied No NJ 8 HW06.12020 NPW GC, ExtJactioll, ECD or HECD, Capillary [SW-846 SOSIA]
Applied No NJ SI-IW06.12030 NPW GC, ExtJaction, ECD or HECD, Capillary: [SW-S46 SOSIA]
Applied No NJ SI-IW06.12040 NPW GC, Extraction, EGD.or HECD, Capillary; [SW-846 S081A]
Celtified Yes NJ SHW06.12050 NPW GC, Extraction, ECD or HECD, Capillary [SW-846 S081A]
Cenificd Yes NJ SHW06.12060 NPW Ge, Extraction, ECD or HECD, Capillary, [SW-846 BOSIA]
Applied No NJ 8HW06.12070 NPW GC, ExtJ-action, ECD or HECD, Capillaryl [SW-S46 S081A]
Applied No NJ SHW06.12080 NPW GC, Extraction, ECD or }IECD, Capillalyl [SW-S46 SOSIA] . I
Applied No NJ SHW06.12090 NPW GC, Ext.raction, ECD or HEeD, Capillary, [SW-846 SOBIA1
Applied No NJ SHW06.12100 NPW GC, Extraction, ECD or HEeD, Capillary' [SW-846 S08IA]
Applied No NJ SHW06.12110 NPW GC, Extraction, ECD or HECD, Capillary; [SW-846 SOS1A]
Applied No NJ SHW06.12120 NPW GC, Extrection, ECD or HECD, Capillary! [SW-S4680SIA]
Applied No NJ SHW06.12130 NPW ac, Extraction, ECD or HECD, Capillary' [SW-S46 S081A]
Applied No NJ SHW06.12140 NPW GC, Extraction, ECD or HECD, Capillalj'; [SW-846808IA)
Applied No NJ SHW06.12150 NPW GC, Extraction, ECD or HECD, Capillalj'i [SW-846 S08IA]
Cettified Yes NJ SHW06.12160 NPW GC, ExtJaction, ECD or HECD, Capillalj': [SW-S46 S08IA]
Allplied No NJ SHW06.12170 NPW GC, Extraction, ECD or HECD, CapillalY , [SW-S46 SOSIA1
KEY; AE = Air and Emissions, BT = Biological Tissues, DW = Drinking Water, NPW = Non-Potable Water, SCM = Solid and Chemical Materials
-Annual Certified Parameters Ust --Effective as of 07/01/2012 until 06/30/2013
: Parametci' Description
Chromium (VI)
Mercury -liquid wa~te
Parameter Descrippoll
Semivolatile ()rganics
Volatile organics i [
I I I ;
Parameter Dcs.cl·ipfloIl ! I , I Aldrin
AlphaBHC
BetaBHC
DeltaBHC
lindane (gamma BHC)
Chlordane (technical)
Chlordane (alpha)
Chlordane (gamma)
I)I)D (4,4'-)
00E(4,4'-)
DDT (4,4'-)
Dieldrin
, Endosulfan I
Endosulfan II
Endoslilfan sulfate
Endrin
Endrin aldehyde
Page 2 of Ii
New Jersey Departnlent of Environmental Protection
National Environmental Laboratory Accreditation Program
ANNUAL CERTIFIED PARAMETER LIST AND CURRENT STATUS
Effective as of 07/01/2012 lIntil 06/30/2013
Laboratory Name: OUTREACH LABORATORY Laboratory Number: OKOOI Activity ID: NLC120001
311 N ASPEN
BROKEN ARROW, OK 74012
Category: SHW06 --Organic Parameters, Cllromutogl'nphy
Eligible to
Report
Status N.JData State Code Mntl'ix Tcchnrque Description Appro\'cd Method
Applied No NJ SHW06.12180 NPW ac, Extraction, ECD or HECD, Capillmy [SW-846808IA]
Certified Yes NJ SHW06.12190 NPW ac, Extraction, ECD or HECD, CapiIlmy [SW-S46808IA]
Applied No NJ SHW06.12200 NPW ac, Extraction, ECD or HEeD, CapilImy [SW-84680SIA]
Certified Yes NJ SHW06.12210 NPW ac, Extraction, ECD or HECD, Capillary [SW-S46 S081A]
Certified Yes NJ SHW06.12220 NPW ac, Extraction, ECD or HECD, Capillary [SW-&46808IA]
Certified Yes Nl SHW06.13110 NPW ac, ExtIaction, ECD or !'lECD, Capillary [SW-846 8082J
Certified Yes NJ SHW06.13120 NPW GC, Extraction, ECD or HECD, Capillary [SW-8468082J
Certified Yes NJ SHW06.13 [30 NPW ac, Extraction, ECD or HECD, Capillary [SW-8468082]
Certified Yes NJ SHW06.13140 NPW GC, Extraction, ECD OJ" HECD, Capillary [SW-846 8082]
Certified Yes NJ SHW06. [3150 NPW ac, Extraction, ECD or HECD, Capillary [SW-8468082]
Certified Yes NJ SHW06.l3160 NPW GC, Extraction, ECD or HEeD, Capillary [SW-846 8082)
Certified Yes NJ SHW06.13170 NPW ac, Extraction, ECD or HECD, Capillary [SW-S46 8082J
Applied No NJ S HWO 6.1 3 i 7S NPW ac, Extraction, ECD or HECD, Capillary [SW-846 8082}
Applied No NJ SHW06. 13 1 SO NPW GC, Extraction, ECD or HECD, Capillary [SW-S46 8082]
Suspended No NJ SHW06.23040 NPW GC, Extl"llction, ECD, Capillary [SW-8468ISIA]
Suspended No NJ SHW06.23060 NPW ac, Extraction, ECD, Capillary [SW-8468151A]
Category: SHW07 -Orgmlic Parallleters, Cbromntograplly/MS
Imglblcto,
Report
Status NJ Data Stllte Code Matrix Technique Description Approved Metbod
Certified Yes NJ SHW07.04010 NPW GC/MS, P & T or Direct Injection, Capillmy [SW-846 8260B]
Applied No NJ SHW07.04011 NPW GCIMS, P & T or Direct Injection, Capillary [SW-S46 8260B]
Applied No NJ SHW07.04012 NPW GCIMS, P & T OJ" Direct Injection, CaplIlary [SW-846 8260B]
Applied No NJ SHW07.04013 NPW GCIMS, P & T or Direct Injec'tion, Capillary [SW-846 8260B]
Applied No NJ SHW07.04014 NPW aCIMS, P & T OJ" Direct Injection, Capillary [SW-846 8260B]
Certified Yes NJ SHW07.04020 NPW Gc/MS, P & T or Direct Injection, Capilluty [SW-8468260B]
Applied No NJ SHW07.04022 NPW GCIMS, P & T or Direct Injection, Capillary [SW-846 8260B]
Applied No NJ SHW07.04023 NPW GC/MS, P & T or Direct Injection, Capillary [SW-846 8260B]
Applied No NJ SHWO? .04030 NPW GC/MS, P & T or Direct Injection, Capillary lSW-8468260B]
Applied No NJ SHW07.04040 NPW aC/MS, P & T or Direct injection, Capillary [SW-8468260B]
KEY: AE = Ai \' lind Emissions, BT = Biological Tissues, DW '" Drinking Water, NPW ~ Non-Potable Water, SCM = Solid and Chemical Materials
--Annual CUltified Parameters List --Effective as of 07/01/2012 until 06/30/2013
,
Parameter Description
Endrin ketone
Heptachlor
Heptllchlor epo;{ide
Methoxychlor
Toxaphene
PCB 1016
PCB 1221
PCB 1232
PCB 1242
PCB [248
PCB 1254
rCB 1260
PCB-1262
PCB-1268
D (2,4-)
TP (2,4,5-) (Silvex)
Parameter Dc.~cription
Benzene
Bromobenzene
Butyl benzene (11-)
Sec-bulylbenzenc
Tert-butylbemene
ChlorQbenzene
Chlorotoluenc (2-)
Chlorotoluene (4-)
Dichlorobenzene (1,2-)
Dichlorobenzene (1,3-)
Puee 3 of II
New Jersey Department of Environmental Protection
National Environmental Laborutory Accreditation Program
ANNUAL CERTIFIED PARAMETER LIST AND CURRENT STATUS
Effective :IS of 07/0112012 uutil 06/30/2013
Laboratory Name: OUTREACH LABORATORY Laboratory Number: OKOOl Activity ID: NLC120001
311 N ASPEN
BROKEN ARROW, OK 74012
Category: SHW07 -Org:lnic Parameters, Cllroinatogrnphy/MS
Eligible to
1 Report
I j Status NJ Data State Code Matrix Tecllnique Description Appr-oved Method Parameter·l>-c.sul]lllon
Certifill<i Yes NJ SHW07.04050 NPW GC/MS, P & T or DirecL Injection, Capillary [SW-846 8260B] Dichlorobenzene (1,4-) I 1
Applied No NJ SHW07.04060 NPW GClMS, P & T or Direct Injection, Capillary [SW-846 8260B] Ethylbenzene !
Applied No NJ SHW07.04065 NPW GC/MS, P & T or Direct Injection, Capillary [SW-846 8260B] Isopropylbellzellc i
Applied No NJ SHW07.04067 NPW GCIMS, P & T or Direct Injection, Capillary [SW-846 8260B] Propylbenzellc (n-)
Applied No NJ SHW07.04070 NPW GC/MS, P & T or Direct Injection, Capillary [SW-846 8260B] Toluene
Applied No NJ SHW07.04071 NPW GClMS, P & T or Direct Injection, Capillary [SW-8463260B] [sopropyltoluene (4-)
Applied No NJ SHW07.04072 NPW GC/MS, I,' & T 01" Dil'cctinjection, Capillary [SW-846 8260B] Trichlorobenzenc (I ,2,3-)
Applied No NJ SHW07.04073 NPW GCIMS, P & T 01" Direct IDj~tion, Capillary [SW-846 8260B] Trimethylbenzene (1,2,4-)
Applied No NJ SHW07.04074 NPW GCIMS, P & T or Direct Injection, Capillary [SW-846 8260B} Trlmethylbenzene (1,3,5-)
Applied No NJ SHW07.04075 NPW GCIMS, P&T, or Direct Injection, Capillary [SW-846 8260C] Trimethylbenzene (1,2,3-)
Applied No NJ SHW07.04080 NPW GC/MS, P & T or Di .. ectInj~ction, Capillary [SW-846 8260B} Xylenes (total)
Applied No NJ SHW07.04081 NPW GCIMS, P & T or Direct Injection, Capillary [SW-846 8260B] Xylene (m-)
Applied No NJ SHW07.04082 NPW Gc/MS, P & T or Directlnj~tioll, Capillary rSW-8468260B] Xylene (0-)
Applied No NJ SHW07.04089 NPW GCIMS, P & T or Direct Injection, CapillalY [SW-846 8260B] Bl'Omochloromethane
Applied No NJ SHW07.04090 NPW GCIMS, P & T or Direct Injection, Capillary [SW-846 8260B] BromodichlOlumetlmne
Applied No NJ SHW07.04095 NPW GCIMS, P & T or Din-ct Injection, Capilliuy [SW-8468260B] Bromoethane
Applied No NJ SHW07.04IOO NPW GClMS, P & T or Direct Inj~ction, Capillary [SW-8468260B] Bromofonn
Certifi(lIi Yes N.I SHW07.04120 NPW GC/MS, P & T or Direct Injection, CapillalY [SW-8468260B] Carbon tetrachloride
ApJllied No NJ SHW07.04130 NPW GC/MS, P & T or Direct 1l1jection, Capillary [SW-846826OB] Chloroethane
Applied No NJ SHW07.04140 NPW Gc/MS, P & T or Direct Injection, CapillslY [SW-8468260B] Chloroethyl vinyl ether (2-)
Certified Yes NJ SHW07.04150 NPW GCIMS, P & T or Direct Injection, Capillary [SW-8468260B] Chloroform
Applied No NJ SHW07.04160 NPW GCIMS, P & T or Direct Injection, CapillalY [SW-846 8260B] Chloromethane
Applied No NJ SHW07.04165 NPW GClMS, P & T or Direct Injection, CapillalY [SW-8468260B] Diethyl ether (Ethyl ether)
Applied No NJ SHW07.04170 NPW GClMS, P & T 01" Direct Injection, Capillary [SW-8468260B] Dichloropropene (trans-1 ,3 -)
Applied No NJ SHW07.04180 NPW GCIMS, P & T or Direct Injection, Capillary [SW-846 8260B] Dibromochlorornethane
Applied No NJ SHW07.04185 NPW GClMS, P & T or Direct Injection, Capillary [SW-8468260B] Dibromoethane (1,2-) (EDB)
Applied No NJ SHW07.04I86 NPW GCIMS, P & T 01· Direct Injection, Capillary [SW-84682608] Dibromomethane
Applied No NJ SHW07.04187 NPW GClMS, P & T or Direct Injection, Capillary [SW-8468260B] Dibromo-3-chlolUpropane (1,2-)
Applied No NJ SHW07.04J90 NPW GC/MS, P & T or Direct Injection, Capillary [SW-8468260B] Dil:hlorodifluoromethane
Applied No NJ SHW07.04200 NPW GClMS, P & T 01· Direct Injection, Capillary [SW-846 8260B] . Dichloroethane ( I ,1-)
Certified Yes NJ SHW07.04210 NPW GClMS, P & T or Direct Injection, Capillary [SW -846 8260B] Dichloroethane (I,2-)
Certifitxi Yes NJ SHW07.04220 NPW GCIMS, P & T 01" Direct Injection, Capillary [SW-846 8260B] Dichloroethene ( I ,1-)
KEY: AE = Air and Emissions, BT = Biological Tissues, DW = Drinking Water, NPW = Non-Potable Water, SCM = Solid and Chemical Materials
---Annual Celtified Parameters List ---Effective as of 07/0112012 until 06/3012013 Palte 4 oflli
New Jersey Department of Environmental Protection
National Environmental Laboratory Accreditation Program
ANNUAL CERTIFIED PARAMETER LIST AND CURRENT STATUS
Effective as of 07/0112012 until 06/3012013
Laboratory Name: OUTREACH LABORATORY Laboratory Number: OK001 Activity ID: NLC120001
311N ASPEN
BROKEN ARROW, OK 74012
Category: SHW07 -Organic Pnllmcters, Chromatogruphy/MS
Eligiblc to
Report
Stntus NJ Data State Code Matrix "fechnrque Description Apjlroved Method
. Applied No NJ SHW07.04230 NPW GClMS, P & T or Direct Injection, Capillary [SW-8468260B]
Applied No NJ SHW07.0423S NPW GC/MS, P & T or Direct Injection, Capillary [SW-846 8260B)
Applied No NJ SHW07.04240 NPW GCIMS, P & T or Direct Injection, Capillary [SW·846 8260B)
Applied No NJ SHW07.04241 NPW GCIMS, P & T or Direct Injection, CapillalY [SW-846 8260B]
Applied No NJ SHW07.04242 NPW GCIMS, P & T or Direct Injection, CapillalY [SW-846 82~OB]
Applied No NJ SHW07.04249 NPW GCIMS, P & T or Direct Injection. Capillary [SW-8468260B]
Applied No NJ SHW07.04250 NPW GC/MS, P & T or Direct Injection, Capillaty [SW-84682$OB]
Applied No NJ SHW07.04270 NPW GC/MS, P & T or Direct Injection. Capilhuy [SW-8468260B)
Certified Yes NJ SHW07.04280 NPW GClMS, P & T or Direct Injection, CapillalY [SW-846 8260B]
Applied No NJ SHW07.04290 NPW GClMS, P & T or Direct Injection, CapillalY [SW-846 82~OB]
Applied No NJ SHW07.04300 NPW GClMS, P & T 01' Direct Injection, CapilJmy [SW-846 82~OBJ
Certified Yes NJ SHW07.04310 NPW GCIMS, P & T or Direct Injection, CapillalY [SW-846 82?OB]
Applied No NJ SHW07.04320 NPW GClMS, P & T 'ol' Direct hijection, CapillalY [SW-846 82?OB]
Applied No NJ SHW07.04322 NPW GC/MS, P & T 01' Direct Injection, Capillary [SW·8468260B]
Applied No NJ SHW07.04325 NPW GCIMS, P & T or Direct Injection, CapillalY [SW-8468260B]
Applied No NJ SHW07.04327 NPW GClMS, P & T or Direct Injection, Capillary [SW-8468260B]
Certified Yes NJ SHW07.04330 NPW GClMS, P & T or Direct Injection, Capillary [SW-8468260B]
Applied No NJ SHW07.04340 NPW GC/MS, P & T or Direct Injection, Capil\alY [SW-846 8260B]
Applied No NJ SHW07.043S0 NPW GClMS, P & Tor DirecllnjectiOll, Capillary [SW-8468260B]
Suspended No NJ SHW07.04360 NPW GClMS, P & T or Direct I1uection, Capillary [SW-846 82~OB]
Applied No NJ SHW07.04365 NPW GC/MS, P & T or Direct Injection, Capillary [SW-846826OB]
Applied No NJ SI-IW07.04370 NPW GClMS, P & T or Direct Injection, CapillalY [SW-846 8260B]
Applied No NJ SHW07.04378 NPW GCIMS, P & T or Direct Injection, Capillary [SW-846 8260B]
Applied No NJ SHW07.04380 NPW GClMS, P & T or Direct Injection, CapillalY [SW-8468260B]
Applied No NJ SHW07.04390 NPW GClMS, P & Tor Direct Injection, Capillary [SW-846 8260B]
Certified Yes NJ SHW07.04500 NPW GClMS, P & T or Direct Injection, Capillary' [SW-8468260B]
Certified Yes NJ SHW07.04530 NPW GClMS, P & T or Direct Injection, Capillary [SW-846 8260B1
Applied No NJ SHW07.04540 NPW GCIMS, P & T 01' Direct Injection, Capillary [SW-8468260B1
Applied No NJ SHW07.04550 NPW GC/MS, P & T or Direct Injection, Capillary [SW·846 8260B]
Applied No NJ SHW07.04560 NPW GClMS, P & T or Direct Injection, Capillaty {SW-846 8260B]
Applied No NJ SHWO'l.04570 NPW GCIMS, P & T or Direct Injection, Capillary [SW-8468260B]
SuspeJlded No NJ SHW07.04580 NPW GClMS, P & T or Direct Injection, Capillary [SW-846 826OB]
KEY: AE = Air and Emissions, BT = Biological Tissues, DW = Drinking Water, NPW = Non-Potable Water, SCM = Solid and Chemical Materials
---Annual Certified Parameters List--Effective as of 07/0112012 until 06/3012013
Parameter Description
Piclllol'Oethene (trans-l,2-)
Dicljloroethene (cis-I ,2-)
Dichloropropane (I ,2-)
Dichloropropane ( 1,3-)
Dichloropropane (2,2-)
Dichloropropene (1,1-)
DichloropropeJ\l~ (cis-I ,3-)
Tetrachloroethane (1,1,2,2-)
Tetrachloroethene
Trichloroethane (I, i,I-)
Trichloroethane (I , i,2-)
Trichloroethene
Trichlorofluoromethane
Trichloro (I, I ,2·) lrifllloroetllane ( I ,2,2-)
'fdchloropropane (l ,2,3-)
'Vinyl acetate
Vinyl chloride
. Acetone
. Carbon disulfide
. Butanone (2-)
,Ethyl acetate
'Hexanone (2-)
N-Nitroso-di-n-bulylallline
,Penlanone (4-rncthyl-2-) (MIBK)
,Methyl telt-butyl ether
Hexachlorobutadiene ( I ,3-)
: Hexachloroethane
'Naphthalene
: Styrene
Tetrachloroethane (1,1, 1,2-)
Tric h lorobenzen e ( I ,2,4-) I'
Nibubenzene j
PalreS ofll
New Jersey Department of Environmental Protection
National Environmental Labol-ntory Accreditation Program
ANNUAL CERTIFIED PARAMETER LIST AND CURRENT STATUS
Effective as of 07/0112012 ulltil 06/30/2013
Laboratol'Y Name: OUTREACH LABORATORY Laboratory Number: OKOOI Activity ID: NLC120001
311N ASPEN
BROKEN ARROW, OK 74012
Category: SHW07 -Organic Pllrmnetel's., Cbromatograplty/MS
Eligible to
Report
Status NJDatn State Code Mlltri,. Techlslquo Dcscrlplion Approved Metllud
Applied No NJ SHW07.05006 NPW Gc/MS, Extract or Dir Inj, Capillary [SW-846 8270C]
Applied No NJ SHW07.05010 NPW GC/MS, Extract 01' nir Inj, Capillary [SW-846 8270C]
Applied No NJ SHW07.05030 NPW GCIMS, Extract or Dir Jnj, Capillary ISW-846 8270C]
Applied No NJ SHW07.05038 NPW GC/MS, Extract or Dir Inj, Capillary ISW-846 827OC]
Applied No NJ SHW07,05040 NPW GCIMS, Extract or Dir Inj, Capillary [SW-846 8270C]
Applied No NJ SHW07.05048 NPW GCIMS, Extract or Die lnj, Capillary [SW-8468270C]
Applied No NJ SHW07.05050 NPW GClMS, Extract or Die lnj, Capillary [SW-846 8270C]
Applied No NJ SHW07.05060 NPW Gc/MS, Extract 01' Dir Inj, Capillary [SW-8468270C)
Applied No NJ SHW07.05062 NPW GC/MS, Exttact or Dir lnj, Capillary [SW-8468270C]
Applied No NJ SHW07.05063 NPW GC/MS, Extract or Dir Inj, Capillary [SW-8468270C]
Applied No NJ SHW07.05070 NPW GClMS, Extract or Dir Inj, Capillary [SW-846 8270C]
Certifkd Yes NJ SHW07.05080 NPW GC/MS, Extract or Dir !nj, Capillary [SW-846 8270C]
Applied No NJ SHW07.05090 NPW GCIMS, Extract or Dir lnj, Capillary [SW-8468270C]
Applied No NJ SHW07.05100 NPW GC/MS, Extract or Dir Inj, Capillary [SW-846 8270C]
Applied No NJ SHW07.05110 NPW GC/MS, Extract or Dir lnj, Capillary [SW-846 8270C]
Applied No NJ SHW07.05115 NPW GC/MS, Extract or Dir rnj, Capillary [SW-846 8270C]
Applied No NJ SHW07.05120 NPW GCIMS, Extract or Dir [nj, Capillary [SW-8468270C]
Applied No NJ SHW07.05130 NPW GClMS, Extract or Dir !nj, Capillary [SW-846 8270C]
Applied No NJ SHW07.05132 NPW GClMS, Extract or Dir Inj, Capillary [SW-8468270C]
Applied No NJ SHW07.05140 NPW-GCIMS, Extract or Die Inj, Capillary [SW-846 8270C]
Applied No NJ SHW07.05150 NPW GClMS, Extract or Dir Inj, Capillary [SW-846 8270C]
Applied No NJ SHW07.05160 NPW GCIMS, Extract or Dir lnj, Capillary [SW-8468270C]
Certifi,~ Yes NJ SHW07.05170 NPW GC/MS, Extract or Dil' !nj, Capillary [SW-846 8270C]
Applied No NJ SHW07.05180 NPW GCIMS, Extract or Dir Inj, Capillary [SW-846 8270C]
Applied No NJ SHW07.05190 NPW GC/MS, Extract or Dir Inj, Capillary [SW-846 827OC]
Applied No NJ SHW07.05200 NPW GCIMS, Extract or Dil' Inj, Capillary [SW-846 8270C]
Applied No NJ SHW07.05210 NPW GClMS, Extract or Dir Inj, Capillary [SW-846827OCl
Applied No NJ SHW07.05220 NPW GC/MS, Extract or Dir Inj, Capillary [SW.·846 8270C]
Applied No NJ SHW07.05230 NPW GClMS, Extract or Dir Inj, Capillary [SW-846 8270C]
Applied No NJ SHW07.0524O NPW GClMS, Extract or Oir bU. Capillary ISW-8468270C]
Applied No NJ SHW07.05250 NPW Gc/MS, Extract or Dir lnj, CapilIalY [SW-846 8270C]
Applied No NJ SHW07.05260 NPW GC/MS, ExtIact or Dir lnj, Capillary [SW-8463270C]
. KEY: AE = Air and Emissions, BT = Biological Tissues, DW = Drinking Water, NPW = Non-Potable Water, SCM = Solid and Chemical Materials
--Annual Certified Parameters List -Effective as of 07/0112012 until 06/3012013
Parameter Descrip.tion
. N-iNitroso-dj-nilropylanl.ine,
; N,NilrosodiphellylamiriJ
Carbazole I
Bimzidine ,
Dlchlorobenzidine (~3'-)
Ahiline I
, CI~loroal1iline (4-)
; Nitroaniline{2-)
~ Nitroanilille (3-)
: Ni,troaniline (4-)
, C~loronaphthalene (2-)
-Hexachlorobenzene
Hexachlorobutlldiene (1.~.)
HexaohloroeYClopentadib~
Hexachloroethane l
Hexachloropropene
Trichlorobenzene (I .2.4-i
Bis (2-chloroethoxy) me ' ne
Bis (2-chloroethyl) eth~
Bis (2-chloroisopropyJ) ether I Chlorophcnyl-phcnyl ctJ~ (~-)
Bromophenyl-phenyl etiler (4-)
Dinitrotoluenc (2,4-) I
Dinitrotoluenc (2,6-) I I lsophorone
Nilrobtnzenr.
Butyl benzyl phlhaJlIle
I I
Sis (2-ethylhexyl) phlh~l\tc
Diethyl phth:llate I
Dimethyl phthal\\te I
Di-n-bulyl phthalate
Di-n-octyl phthalate I
I
I
I
Page 6 or! II
New Jersey Department of Environmental Protection
National Environmental Laboratory Accreditation Program
ANNUAL CERTIFIED PARAMETER LIST AND CURRENT STATUS
Effective as of 07/0112012 until 06/30/2013
Laboratory Name: OUTREACH LABORATORY Laboratory Number: OKOOI Activity ID: NLC120001
311 N ASPEN
BROKEN ARROW, OK 74012
Category: SHW07 -Organic Pnrnmeters, Chromatogl"llphy/MS
Eligible to
Report
Status NJ Data Stllte Code Mutrix Technique Description Approved Method
Applied No NJ SHW07.05270 NPW GClMS, Extract or Oir lnj, Capillary [SW-8468270C]
Applied No NJ SHW07.05280 NPW GCIMS, Extract or Oil' Inj, Capillary [SW-8468270C]
Applied No NJ SHW07.05290 NPW GClMS, Extract 01' Oir lnj, Capillary [SW-846 8270C]
Applied No NJ SHW07.05300 NPW GC/MS, Extract 01' Oir 111j, CapiIJaty [8W-846 8270C]
Applied No NJ SHW07.05310 NPW GCtMS, Extract or Oir 111j, CapillalY [SW-8468270q
Applied No NJ SHW07.05320 NPW GC/MS, Extract or Dir lnj, Capillary [SW-8468270q
Applied No NJ SHW07.05330 NPW GClMS, Extmct or Dir Il1j, Capillary [SW-846 8270C]
Applied No NJ SHW07.05340 NPW GCIMS, EXllact or Oir Il1j, Capillat), [SW-8468270C]
Applied No NJ 8HW07.05350 NPW GC/MS, Extract or Oil' Il1j, Capillal), [8W-846 8270C)
Applied No NJ SHW07.05360 NPW GClMS, Extract or Dir Inj, Capillary [SW-846 8270C]
Applied No NJ SHW07.05370 NPW GC/MS, Extract 01' Dir Inj, Capillary [SW-846 8270C]
Applied No NJ SHW07.05380 NPW GCIMS, Exliact or Oil' Inj, CapiIJmy [SW-8468270C)
Applied No NJ SHW07.05390 NPW GC/MS, Extlact or Oir Inj, Capill:l1)' [SW-846 8270C]
Applied No NJ SHW07.05410 NPW GCIMS, Elltract or Dir Inj, Capillary [SW-846 8270q
Applied No NJ SHW07.05420 NPW GC/MS, Extract or Dir Inj, Capillary [SW-846 8270C]
Applied No NJ SHW07.05430 NPW GCIMS, Exttact or Oir Inj, Cnpillary [SW-8468270C]
Applied No NJ SI-1W07.05440 NPW GC/MS, Extract or Dir Iqj, Capillary [SW-8468270C]
Applied No NJ SHW07.05450 NPW GClMS, Extract or Dir Inj, Capillary [SW-8468270C]
Applied No NJ SHW07.05460 NPW GClMS, Extract or Oir Inj, Capillary [SW-8468270C]
Applied No NJ SHW07.05470 NPW GCIMS, Extlact or Oir Inj, Capillary [SW-8468270C]
Applied No NJ SHW07.05480 NPW GC/MS, Extract 01' Oil' 11Ij, Capillary [SW-8468270C]
Applied No NJ SHW07.05490 NPW GC/MS, Extmet or Oil' Illj, Capillaty [SW-8468270C]
Certified Yes NJ SHW07.05500 NPW GClMS, Extract or Dir Inj, Capillary [SW-846 8270C]
Celtified Yes NJ SHW07.05510 NPW GC/MS, Extract or Dir Inj, Capillary [SW-846 8270C]
Applied No NJ SHW07.0S520 NPW GC/MS, Extract or Oir Inj, Capillary [SW-8468270C]
Applied No NJ SHW07.05530 NPW GClMS, Extract or Dir Illj, Capillaty [SW-846 8270C)
Certified Yes NJ SHW07.05540 NPW GClMS, Extract or Dir Inj, Capillary [SW -846 8270C]
Applied No NJ SHW07.0S5S0 NPW GC/MS, Extract or Dir Inj, Capillary [SW-846 8270C)
Certified Yes NJ SHW07.05560 NPW GClMS, Extraet or Oir Inj, Capillary [SW-846 8270C]
Certified Yes NJ SHW07.05570 NPW GC/MS, Extract 01' Oil' Inj, Capillary [SW-846 8270C]
Certified Yes NJ SHW07.05590 NPW GClMS, ExGract or Die Tnj, Cnpillary [SW-8468270C]
Applied No NJ SHW07.05600 NPW GClMS, Extract or Oil' IlIj, Capillmy [SW-8468270C]
KEY: AE = Air and Emissions, BT = Biological Tissues, DW = Drinking Water, NPW '"' NOll-Potable Water, SCM = Solid and Chemical Materials
--Ann\lal Certified Pal'ameten; List --Effective as of 07/0112012 until 06/3012011
Parameter Description
Acenaphthene
Anthracene
Acenaphthylene
Benzo(a)antbracene
Benzo(a}pyrelle
Benzo(b )fluorRnthene
Ben:zo(ghi)pelylenc
Benzo(k)f1uoranthene
Chl),sene
Dibenzo(a,h}.1nthracel1e
Flllol7lllthene
Fluorene
lndeno( I ,2,3-cd)pyrene
Naphthalene
Phenanthrene
Pyrene
Methyl phenol (4-chlol'O-3-)
Chlorophenol (2-)
Dichlol'ophenoJ (2,4-)
OimethylphenoJ (2,4-)
Dinitrophenol (2,4-)
Dini(rophenol (2-methyJ-4,6-)
Methylphenol (2-)
Methylphenol (4-)
Nitrophenol (2-)
Nitropbenol (4-)
Pentachlorophenol
Phenol
Trichlorophenol (2,4,5-)
Trichlorophellol (2,4,6-)
Methylphenol (3-)
Oibenzofuran
Page 7 of II
New Jersey Department of Envirollmentnl Protection
National Environmental Laboratory Accreditation Prog.·am
ANNUAL CERTIFIED PARAMETER LIST AND CURRENT STATUS
Effecth'c as of 07/01/2012 IIntil 06/3012013
Laboratory Name: OUTREACH LABORATORY Laboratory Number: OKOOI Activity ID: NLC120001
311N ASPEN
BROKEN ARRow,loK 74012
Cntegnry: SHW07 -Ol'g~llic Pnrnmctcl"S, Chl'omalogropby/MS
Eligiblc to
Report
Status NJ Dota Stille Codc Matrix Technique Descriptiob Approved Method
Applied No NJ SHW07.05691 NPW GCIMS, Extract or Dir lnj, Capillary [3W-8468270C]
Applied No NJ SHW07.05692 NPW GCIMS, Extrnct or Oir [nj; Capillary [SW-846 8270q
Applied No NJ SHW07.05700 NPW GClMS, E.xlmct or Dir Inj, Capillary [SW-846827OCl
Applied No NJ SHW07.05710 NPW GCIMS, Extract or Dir Tnj. CapiIla1y [SW-846 8270C]
Applied No NJ SHW07.05725 NPW GCIMS, Extract or Dir Illj, Capillary [SW-84682700]
Applied No NJ SHW07.05730 NPW GClMS, Extmct or Dir Inj, Capillary [SW-84682700]
Certified Yes NJ SHW07.05750 NPW GClMS, Extmct or Oir luj, Capillary [SW-8468270C]
Category: WPP09 -Radiochem.: R."Idloactivity I Radiouudide
Eligible to
Report
StnlUs. NJ Data State Code Matrix TccllDiqul! Descrlptlo!l Approved Method
Certified Yes NJ WPP09.0IOOO NPW Proportional or Scintillation [EPA 900]
Celtificd Yes Nl WPP09.0300D NPW Proportional Counter [EPA 900]
Ce11ificd Yes NJ WPP09.03100 NPW Gamma Spectrometty [EPA 901.1]
Celtified Yes NJ WPP09.03200 NPW Gamma Spectrometry [EPA90I.I]
Certified Yes NJ WPP09.03300 NPW Gamma Spectrometry [EPA 90Ll)
Cettified Yes NJ WPP09.05000 NPW Precipitation [SM 7S00-Ra B]
Cel1ificd Yes Nl WPP09.06000 NPW Radiochemical [SM 7500-Ra B]
Certified Yes NJ WPP09.06020 NPW Co-Precipitation 1 Be1a Counting [EPA 904.0]
Certified Yes NJ WPP09.07000 NPW Ganuna SpectrometlY [EPA 901.1]
Applied No NJ WPP09.08000 NPW Precipitation I Beta Counting (EPA90S.0]
Certified Yes NJ WPP09.08!OO NPW Precipitation 1 Beta Counting [EPA 905.0]
Celtified Yes NJ WPP09.09000 NPW Co-Precipitation I Alpha Counting [USERDEFrNEDASTM 05174-91]
Certified No NJ WPP09.09010 NPW Isotopic Analysis I Alpha Spectrometry [ASTM D 3972]
Applied No NJ WPP09.09020 NPW Laser Phosphorimetry [ASTM D5174]
Certified Yes NJ WPP09.10000 NPW Djsti1lati~Liquid Scintillation [EPA 906.0]
Applied No NJ WPP09.l1000 NPW Radiochemical! Alpha Counting [EPA 907.0]
KEY: AE ~ Air and Emissions, BT = Biological Tissues, DW = Drinking Water, NPW = Non-Potable Water, SCM = Solid llnd Chemical Materials
-Annual Certified Parnmeters List -Effective as of 07!0 [/2012 until 0613012013
Parameter [)(!scrlp,ion
Dichlol'Obenzcne (1,2-)
Dichlorobenzene (1,3-)
Dichlorobenzene (1,4-)
Benzoic acid
Dec:me (n-)
Octadecane (n-)
Pyridine
Parameter DascrlpUon
Gross -alpha
Gross -bela
Cesium 134/137
Cobalt 60
Zinc 65
Radium -total
Radium-226
Radium-228
Photon Emitters
Strontium -89, 90
Strontium -90
Uranium
Umnium
Uranium
Tritium
Plutonium
Page 8 of 11
New Jersey Department of Environmental Protection
National Environmental Laboratory Accreditation Program
ANNUAL CERTIFIED PARAMETER LIST AND CURRENT STATUS
Effective as of 07/01/2012 until 06/30/2013
Laboratory Name: OUTREACH LABORATORY Laboratory Number: OKOOI Activity ID: NLC120001
311 N ASPEN
BROKEN ARROW, OK 74012
Category: WPPIO -Radon ill Wastewater
Eligible to
Report
Stntus NJData State Code Mlltrix Technique Dcseril?tioll Approved Method
Celtified Yes NJ WPPIO.OIOOO NPW Liquid Scintillation (USER DEFINED SM 7500)
Category: SHW02 --Cl,aractel'istics of llnzardolls Waste
ICliglblc to
Report
Status NJData Stille Code Matrix Teclmique Des<lrlE I rOll Appnved Method
Certified Yes NJ SHW02.01000 NPW,SCM Pensky Martens [SW-846 1010)
Certified Yes NJ SHW02.03000 NPW,SCM Aqueous Waste, Potentiomehic [SW-8469040B]
Certified Yes NJ SHW02.06900 NPW,SCM TCLP, Toxicity Procedure, ZHE [SW-846 \311)
Certified Yes NJ SHW02.07000 NPW,SCM TCLP, Toxi.city Procedure, Shaker [SW-8461311)
Celtified Yes NJ SHW02.08000 NPW,SCM Synthetic P.PT Leachate Procedure [SW-846 1312]
Category: SHW04 -Inorganic Parameters
Eligible to
Report
Status N.JDntn Stnte Codc Matrix Techniquc Description Allproved Method
Certified Yes NJ SHW04.05000 NPW,SCM ICP [SW-8466010B]
Certified Yes NJ SHW04.06500 NPW,SCM rcp [SW-84660IOB]
Certified Yes NJ SHW04.09000 NPW,SCM ICP [SW-846601OB)
Certified Yes NJ SHW04.11500 NPW,SCM ICP [SW-8466010B)
Certified Yes NJ SHW04.13500 NPW,SCM ICP [SW-8466010B)
Certified Yes NJ SHW04.1SI00 NPW,SCM rcp [SW-84660IOB)
Certified Yes NJ SHW04.IS500 NPW,SCM ICP (SW-8466010B)
Certified Yes NJ SHW04.17500 NPW,SCM ICP [SW-8466010B)
Certified Yes NJ SHW04.18500 NPW,SCM ICP [SW-84660IOB]
Certified Yes NJ SHW04.22500 NPW,SCM ICP [SW-8466010B)
Certified Yes NJ SHW04.24500 NPW,SCM ICP [SW-8466010B)
Certified Yes NJ SHW04.26000 NPW,SCM ICP [SW-84660IOB)
Certified Yes NJ "SHW04.27500 NPW,SCM ICP [SW-8466010B]
Certified Yes NJ SHW04J0500 NPW,SCM ICP [SW-8466010B)
Certified Yes NJ SHW04.31500 NPW,SCM ICP [SW-8466010B]
KEY; AE = Air and Emissions, BT = Biological Tissues, OW = Otinking Willer, NPW = NOll-Potable Water, SCM = Solid and Chemical Materials
--Annual Certified Parameters List ---Effective as of 07/0112012 until 06/3012013
Pnrnmcter Descl"iption
Radon
Parameter Deseription
Ignitability
Corrosivity -pH wasle, >20% waler
Volatile organics
Metals
Metals -organics
Parameter Description
Aluminum
Antimony
AlSenic
Barium
Beryllium
Boroll
Cadmium
Calcium
Chromium
Cobalt
Copper
Iron
Lead
Magnesium
Manganese
Pal>f~ 9 nf' II
Nevr Jelosey Department ofE:ovironmental Protection
NatioD,al Environmental LaborntOloy Accreditation Program
ANNUAL CERTIFIED PARAMETER LIST AND CURRENT STATUS
Effettive as of 07/011201211ntil 06/30/2013
Laboratory Name: OUTREACH LABORATORY Laboratory Number: OK001 Activity ID: NLC120001
311 N ASPEN
BROKEN ARROW, OK 74012
Category: SHW04 -lnorganic Pnramelers
Eligible to
RepOIot
Status NJ Data State Code Matrix
Celtified Yes NJ SHW04.34000 NPW,SCM
Celtified Yes NJ SHW04.35500 NPW,SCM
Certified Yes NJ SHW04.38000 NPW,SCM
Certified Yes NJ SHW04.39000 NPW,SCM
Certified Yes NJ SHW04.41000 NPW,SCM
Celtified Yes Nl SHW04.43000 NPW,SCM
Cel1itied Yes NJ SHW04.44000 NPW,SCM
CCI1ified Yes NJ SHW04.45000 NPW,SCM
Certified Yes NJ SHW04.47500 NPW,SCM
Certified Yes NJ SHW04.49000 NPW,SCM
Category: SHW09 -Miscellaneous Parnmeters
Eligible to
Report
Stntus NJDnta St.tte Code Matrix
Applied No NJ SHW09.02000 NPW,SCM
Applied No NJ SHW09.04100 NPW,SCM
Category: SHW04 -Inorganic Parameters
Eligible to
Report
Stlltus NJ Data State Cod&:! Matrix
Certified Yes NJ SHW04.03000 SCM
Certified Yes NJ SHW04.33500 SCM
Category: SUW05 -Orgallic Parameters, Prep. 1 Screening
Eligible to
Status
Applied
Certified
Report
NJ Data State Code
No
Yes
Nl
NJ
SHWOS.05000
SHW05.12000
Mntrix.
SCM
SCM
Technique DescriJiUoll
ICP
ICP
ICP
ICP
ICP
IC?
ICP
ICP
ICP
ICP
Techniquc Description
Distillation
TitrimetriclManual Spectrophotometric
Technique Description
Acid Digestion, Soil Sediment & Sludge
AA, MalUlal Cold Vapor
Tcclmiquc Description
Ultrasonic Extraction
Cleanup-Florisil
Ap-Pl'()ved Metbod
[SW-84660109]
[SW-84660109]
[SW-8466010B)
[SW-8466010B]
[SW-8466010B)
[SW-8466010B]
[SW-8466010B]
[SW-8466010B]
[SW-84660IOB)
[SW-8466010B]
Allproved Method
[SW-846901OC]
[SW-846 9014]
Appro'l'ed Method
[SW-846 3050B}
[SW-846 7471A]
Approved Method
[SW-8463550B)
[SW-8463620B]
KEY: AE =' Air and Emissions, BT = Biological Tisslles, DW'" Drinking Water, NPW = Non-Potable Water, SCM'" Solid and Chemical Materials
--Annual Certified Parnmeters List ---Effective as of 07/0112012 until 06/30/2013
Parameter l)el.cription
Molybdenum
Nickel
Potassium
Selenium
Silver
Sodium
Strontium
Thallium
Vanadium
Zinc
Parameter DescrIption
Cyanide
Cyanide
Parametcr Description
Metals
MercuIY -solid waste
Parameter Description
Semivolatile organics
Semivolatile ol'gani<:s
Page 10 of 11
I I Ne,~ Jersey Dep"artment of Environmental ProtecHon
National Environmental Laborntory Accreditation Program I ANNUAL CERTIFIED PARAMETER LIST AND CURRENT STATUS
Laborntory Name: OUTREACH LABORATORY
311 N ASPEN
BROoKEN ARROW, OK 74012
Category: SHWOS -Organic Parameters, Prep. f SCI'eening
Eligible to
]R.CPOI·t
Slatus NJDntn State Code Matrix
Certifi(:d Yes NJ SHWOS.17000 SCM
Cnteglll-Y: SHW09 -Miscellanoolls Parameters
Eligible to
Report
Status NJData Stnte Code Matrix
Certified Yes NJ SHW09.60000 SCM
Celtificd Yes NJ SHW09.60105 SCM
Cel1ified Yes NJ SHWO!>.60106 SCM
Celtificd Yes NJ SHW09.601lO SCM
Cel1ified Yes NJ SHW09.60120 SCM
Celuficd Yes NJ SHW09.60130 SCM
Certified Yes NJ SHW09.60140 SCM
Certified Yes NJ SHW09.601S0 SCM
Certified Yes NJ SHW09.60160 SCM
Cel1ified Yes NJ SHW09.60200 SCM
Certified Yes NJ SHW09.60300 SCM
Certified Yes NJ SHW09.60310 SCM
Certified Yes NJ SHW09.60400 SCM
Effective as of 07/01/2012 until 06/3012013
Laboratory Number: OKOOI Activity ID: NLC120001 I
TcclmllJuc DciSc:.rlptlOJI Approved Method
Cleanup-Sulfuric AcidlKMn04 [SW-8463665A]
J
TcclJ DlqllcDescripflo» Approved Method
Pl'oportio~al Counter [SW-8469310]
Radon Emanation [DOE Ra-04]
Precipitation [5M 7500-Ra B]
PI'l:cipitlltlon [SW-8469320)
Gamma Spectromelly [DOE 4.5.2.3J
Gamma spectrometry [DOE 4.5.2.31
Gamma SpeetlUmetry [DOE 4.5.2.3]
Gamma Spectrometry [DOE 4.5.2.3]
Gat1Ul1a SpectlUmetly [DOE 4.5.2.3) [USER DEFrNED HASL
Ga-OJ-Rl
Precipitation f Beta Counting [DOE Sr-Ol, 5[-02]
FluoromebY [ASTM D 5174]
Alpha SpectrometlY [DOEU-02]
Alpha SpectrometlY [DOE 4:5.5]
KEY: AE 0: Air and Emissions, BT 0: Biological Tissues, DW = Dlinking Water, NPW = Non-Potable Water, SCM = Solid and Chemical Materials
--Annual Certified Parameters List --Ef1ective as of 07/01/2012 until 06130120:13
Parameter DC$O"lptlon
Semivolatile organics
Parameter Dest:l'rption
Gross -alplla-bela
Radium -226
Radium-226
Radium -228
Cesium 134/137
Cobalt 60
:Zinc 65
Bnrium 133
Phalon Emitters
Strontiulll -89, 90
Uranium
Uranium
TI10riUtn
Joseph F. Aiello, Man~ger ,
I
Page 11 of II
State of New Jersey
Department of Environmental Protection
Certifies That
Outreach La6oratory
Laboratory Certification ID # OK001
is hereby approved as a
Nationally Accredited Environmental Laboratory
to perform the analyses as indicated on the Annual Certified Parameter List
which must accompany this certificate to be valid
having duly met the requirements of the
Regulations Governing The Certification Of
Laboratories And Environmental Measurements N.J.A.C. 7:18 et. seq.
and
having been found compliant with the 2009 TNI Standard approved by the
The NELAC Institute
Expiration Date June 3D, 2014
NJDEP is a NELAP Recognized Accreditation Body
This certificate is to be conspicuously displayed at the laboratory with the annual certified parameter list in a location on the premises visible to the public.
Consumers are urged to verify the laboratory's current accreditation status with the State of NJ, NELAP.
New Jersey Department of Environmental Protection
National l~nvironmcntal Laboratory Accreditation Program
ANNUAL CERTIFIED PARAMETER LIST AND CURRENT STATUS
Effective liS of 07/01120 lJ until o 6/3 fl.'lO J 4
!\borntory Name: OUTREACH LABORATORY Laboratory Number: OKOOI Activity In: NLC130001
11 N ASPEN
ROKEN ARROW, OK 74011
icgor) : SDW07 -RadiochcllI.: Rlldiollctivil) / Rmlionnelidc
lhlS
!iillt:d
rtil1cd
!1ilicd
rtilied
['Ii Ited
!tii'it:d
rlificd
Itilied
liiilcd
(tifled
rti!ied
rtified
.tilied
,tegory:
IIIIS
rtificd
Eligible 10
Report
NJ Dnlll Slale Code
Yes NJ SDW07.01000
Yes NJ SOW07.01001
Yes NJ SDW07.02000
Yes Nj SOWD7.03000
Yes NJ SDW07.03100
Yes NJ SDW07.D3900
Yes NJ SDW07.041 DO
Yes NJ SDWO? .05000
YeS NJ SOW07.06000
Yes NJ SDW07.06010
Y(:5 NJ SDW07.07000
Yes NJ SOW07.D8200
Yes NJ SOW07.08300
SDWOR --Rndoll ill Drinking Walei'
Eligible to
Report
NJ Dahl Slate Code
Yes NJ SOW08_0 I 000
Mllldx
OW
OW
OW
OW
DW
OW
DW
OW
DW
DW
OW
OW
DW
Mnlrix
OW
Itc~Ol'y: SIIW02 -Churnelcristlcs of Jl:l:I:anlous Wnste
Eligible to
Rcporl
Ilus N.J Ouln Stnte Colic
Itilted Yes NJ SHW02.06950
Itcgor)': SIIW04 -lllorganic P!lrmnclers
Eligihlc 10
Report
lhlS N,\ Dlllu Slnlc Code
rtilicd y"" NJ SHW()4.0 J 500
Matrix
NPW
Malrix
NPW
Technique Description
Propm'liunal or SCilllillutioll
48-J-Iollt' Rapid Gross Alrlm T~,\
Rallinchelllica I
Gamma Spectrometry · Rndio~hcmistry
Gamm" Spectrometry
Radiocbemical
Precipil,lliol1
Precipilation
Total Sr &. Strontium 90
Strontium 90
DislilJ~lion/Liquid Scinlillnlion
Las_cr Phosphorimclly
Alplm Spectrometry
Tecl}1\iiJu~ Description
Liquid Scinli!iatillll
TcchllllJIlC Descd£lion
TellO, Toxicity Procedure, Shnkcr
Techniqlle Description
Acid Dig~slinn/AqlJeou, Sm\lple~, ICP, rLAA
Approved lV;.:t.:.:ct.::.IH::..:":..1 _______ _
[EPA 900.0J
[OTHER ECLS-R-Gt\J
[EPA 902.0J
[EPA 901 .0]
{EPA 901.1]
ISM 7500-RB B1
[EPA 904.01
ISM 7500-Rn BJ
[EPA 905.0]
[EPA 905.0]
[EPA 906.0)
[ASTM D5174]
[ASTM D 3972)
Approved Method
[SM 7500-I~n]
APP"{lwll Melh!)(1
[SW-846 1311]
Approved ~1_O_rl ______ _
[SW-846 ]0 i 011]
;:'1': AE = Air ami El1lission~, BT = Biological Tissues, OW = Drinking WaLer, NPW = NOJl"PolnbJe Waler, SCM = Solid and Chclllicnl /vlalcri:Jis
~" IIIC.!.:~:,pc5cri~II(Jn
(jro~.s . nlphil-hcm
Gwss . ;;lpb (ind. Ru & U excL mUDn)
Rnuiom;livc iOdine
C.:;;iu;n 1J4/ I J7
GHJJUm. emilW)S
RnllilJln -'22 6
Rntli\ll1J ·2?R
R;diml1" (OIU!
Stro!llitlm -89 , 90
Strontium .. 90
TritiuJl1
ijl11niul'r.
U,m:iulI!
l'arallIdcr Description
Radon
I'arlllllcicr D"scdJlti~
SemivDi;ltilc ')rgunics
Parameter Description
Metals. TOi,,1
Pa~e I ill' I !
New Jersey Department of :U;nvironmcntal Protection
National Environmental Laboratory Accreditation Program
ANNUAL CERTIFIED PARAMETER LIST AND CURRENT STATUS
£ITcctive us of 07/01/2013 until 06/3012014
Jabol'atory N lime: OUTREACH LABORATORY Laboratory Number: OK001 Activity ID: NLC 13000 I
'll N ASPEN
mOKEN A.RROW, OK 74(l1Z
'atcgury: SIIWt)4 -Inurgallic Par:lIl1cters
'-'~ligiblc 10
neport
lalus
crtificd
N.I Data Stille Coile Malrix Techni(tllc De~crifltioll
y~s NJ SI-lW04.J3000 NPW
:!liegory: SBWIJ5 --Orgallic Pnrameters, Prep. I SCI"cCllillg
Eligible 10
Reporl
latus NJ Datu Siale Code Malri:>;
cr(iIlctl
crlilicd
Yes
Yes
NJ
NJ
SHW05.01000
SHW05.07000
NPW
NPW
::tlcgor'Y: 811W06 -Orgauic Parameters, Chromalography
Eligihlc to
Report
tal liS N.' Data State Cude Matrix
pplictl No NJ SHW06.12010 NPW
pplicd No NJ SHW06.12020 NPW
.pplicd No NJ SHW06.12030 NPW
,pplied No NJ SHW06, i 2040 NPW
:tltiJ'icu Yc.'; NJ SHW06.i2050 NPW
\!11iJicd Yes NJ SHW06.12060 NPW
,ppliccl No NJ SHW()6.12070 NPW
,ppli(;d No NJ SI-IW06. 1 2080 NPW
,pplicd No NJ SHW06.12090 NPW
.ppliccl No NJ SHW06.12100 NPW
.pplicd No NJ SHW06.12l10 NPW
,pplicd No NJ SHW06.12120 NPW
.pplicd ND NJ SI-IW06.12130 NPW
,ppJicd ND NJ SHW06.12140 NPW
.pplicd No NJ SHW06.12150 NPW
:crtilkti Yes NJ SHW06.12160 NPW
.pplicd No NJ SHW06.12170 NPW
.pplicd No NJ SHW06.12180 NPW
AA, Manual CDid Vapor
Technitillc #.$',;. _'.:..1 I_I I_u_, " _________ _
Scpmatory Funllel Exlraction
Purge & Trap Aqueous
TecJl1lil)lI~ r'';7cl'':,tioll ----GC, E.xtmctiol!. ECD or HECD, Capillury
(iC, Exllilclion, ECD or HECD, Capillnry
GC, Extr.Jclioll, [CD or HECD, CnpiJl~lY
GC, Extmction, ECO or j'IECD, CnpillalY
GC, ExtJ<1Clioll, ECD Dr HECD, Capillary
GC, Exll"ilction, EeD or HECD, Capillary
GC, Extmclion. EeD or HEeD, Capil!nry
Ge, EXlral:liDl1, ECD or HECD, Capilhll"Y
GC, EXlmclion, ECD or HECD, Capillary
GC Exlrnclion, ECD Dr HECD, Capill"'y
ce, ExtnlClioll, ECD or HEeD, CnpiIIury
GC, EXlrnclion, EeO or HECD, Capillary
GC, Extraclion, ECD or HECD, Capillnry
GC, ExtlUclion, ECD or HEeD, C .. pillalY
GC, Exll,lcti(Jl1, ECD or HECD, CapilhllY
GC, EXll';lClioll, Eeo or 1·1 ECD, Capillnry
ac, btrnclion, ECD or HEeD, C"pillnry
GC. Extraction, EeO or HECD, Capillary
Approved Mellioll
[SW ·R46 7470;\1
AIJ!'rnvcd Method
[SW-846 35! OC]
[SW-8·J650]08j
l\r.p.o\·~:l Method
[S W-R46 8081 II]
[S W .. 846 808!)\ 1
[SW-R46808IA1
[SW·846 8081 A I
[SW·8'16 80Sl;\J
[SW·~46 W8IA]
[SW-846 S08l A]
[5W-846 8081 r\]
[SW-8<lo SOg! J\]
[SW-S46 808 j /\]
(SW-Il<l6 8081 A]
(SW-846 H081 AJ
[SW-B46 8081 AJ
[SW-846 8081 AI
[SW-S4680SJA]
[SW-846 R081 A]
[SW-846 80S I AI
[SW-S46 8D81 A]
~EY: AE = Air and Emissions, BT = Biological Tissue:;, OW = Drinking Water.. NPW = NOIl-Po,able Wnler, SCM -Solid om1 ChemiC'll M<llcrinls
.-... . f'\~11f'11""1") ••• ~,:I nr.J1n/'1i)t.!
______ P_lI_r_"llletcr Description
Mt:rcillY . JiqHil1 wasle
Pnf'lIn1clc,· '~""h'ilUll
,:;:(:Inivoinlilu ofl,(.mic5
Vubti:t; org:lll!tS
Pnran,ctcr .!lit! &lliuu
Aldrin
r\lnhu 8HC
8\:1\\ BHe
Dcll\l SHe
Lindane (g;]1I1Il1[l BI-1C)
Cillonl,m(; f.tc!;hnical)
Chlordanu (njphn)
Chlordalle (gUllllllll)
DDD (4,<\'-)
DOE (11,4'-)
DDT (4A"~1
Diddrin
ElldoSlll iiln i
Endo~lIi ran JI
Elld\)S\lIlllll sulitllC
Endrill
Emlrin :lldehyde
Cmlrin k~loll(;
--~----~-
Pngc'2 or 11
New Jersey Department of Environmentnl Protection
Natiolllll Environmental Laboratory Accreditation Program
ANNUAL CERTIFIED PARAMETER LIST AND CURRENT STATUS
Effective us of' il7/0112013until 06/30i2014
aboratory Name: OUTREACH LABORATORY Laboratory Number: OKOOI Activity ID: NLC130001
11 N ASPEN
ROKEN ARROW, OK 74012
-----
I(!':gory: SHW()6 -Orgllllic Pl1rnmctcrs, Chromatography
Eligible to
Report
Itus NJ Dolo Stllte Code Mntrix Technique Description ApfJrovcd Method
rtifietl Yes NJ SHW06.12190 NPW Ge, Exlraction, ECD or HECD, Cupillary [SW-846808IA]
,plied No NJ SHW06.12200 NPW GC, EXtl~lCtiol1, ECD or HEeD, CnpilJ:;ry [SW-846808IA]
(tined Yes NJ SHW06.12210 NPW GC, Extruction, ECD or HECD, Capillnly [SW-846 SORIA]
ltified Yes NJ SHW06.12220 NPW GC, Extmction, ECD or HECD, Capillary [SW-846 8081 A]
llificd Yes NJ SHW06.1:l1 iO NPW GC, Extraction, ECD Dr HECD, Capillary (SW -846 8082]
rtilied Yes NJ SHW06.13 120 NPW GC, Exl.mclion, ECD or HECD, Capi11l1ry [SW-846 8082]
rtilied Yes NJ SHW06.!3130 NPW Ge, Extraction, ECD or HECD, CnpilhlJY [SW-8468082]
llified Yes NJ SHW06.IJI40 NPW GC, Extmc(ion, ECD or HECD, Capillmy fSW-846 8082]
11ified Yes NJ SHW06. j 3150 NPW GC, EXll1lclioll, EeD or HECD, Cnpilllll)' [SW-84680H2]
rtilicd Ycs NJ SHW06.13160 NPW GC, ExtrJclioll, ECD Dr HECD, Capillary [SW -8468082]
11ilied Yes NJ SHW06.13170 NPW GC, Extl1lction, ECD 0; HECD, CapillalY [SW-846 8082]
Iplied No NJ SHW06.I3J75 NPW GC, Exlntctioll, ECD or HECD, Capilinry [SW-8468082]
Iplied No NJ SHWD6.l318D NPW GC, Exlmciion, ECD or HECD, Capillmy [SW-846 8062]
Iplied No NJ SHW06.230<l0 NPW GC, EXli<lctioll, ECD, Cnpil1ary [SW.-846 S 151 A]
lplied No NJ SHW06.23060 NPW GC, Extraction, ECD, Capillary [SW-846815IA]
Ilcgory: SliW07 -Orgllnic Pllrllmeters, Chromlitogrnphy/MS
Eligible to
Report
alliS NJ Dntn State Code Mlltrix TechniQue D~scriptlo_n_ APlll'O~II~ • __
:rtili~'(1 Yes NJ SHW07.04010 NPW GC/MS, P &. Tor Direct Injection, Capillnry [,SW-8468260B]
lfJliell Nt) NJ SHW07.04011 NPW GC/MS, P &. T Dr Direct Injection, Cupillnry [SW.·8468260B]
)plil!d No NJ SI·IW07.04012 NPW GC/MS, P &. T or Direct Inj~clion, Capilla,y [SW-8468260B]
)plied No NJ SHW07.04013 NPW GC/MS, P &. T or Direct Injection, C;lpill:try [SW-8468260B]
)plied No NJ SHW07.04014 NPW GClMS, P &. T or Direct Injection, Capillary [SW-84682608]
:ltilictl Yes NJ SJ-IW07.04020 NPW GC/MS, P & T or Direct Injectioll, Copillmy [SW-84682{)OB]
lplied No NJ SHW07.04022 NPW GC/MS, P & T or Direci h1jcclion, CapilialY [SW-8'16 8260B]
)plied No NJ SHW07.04023 NPW GC/MS, P &. T or Direcl Injection, Cupillmy [SW-R468260B]
)plied No NJ SI-IW07.04030 NPW GClMS, P & T or Direct Injection, Cupillnry [SW-8468260B]
lpli<:d No NJ SHW07.04!J.:10 NPW GClMS, P &. T or Direct Injection, C;lpiIhlry [SW-R46 826081
:Itilied Yes NJ SHW07.04050 NPW GC/MS, P & T Ill' Direct Injectioll, Cnpillar)' [SW-846 821i0B]
EY: AE = Air "nd Elllbsions, BT = Biolugical Tisslles, DW = Drinking Water, NPW = Non-Po\nble W<ller, SCM = Solid ;lml Chcmicnl Miltcdals
0" " ...... ",.,,,,., .. n .l.r rli'\M:"" , t
-----.
.~'
ParJl meier D~:':iptltm
Hepinchlor
Heplm:hlor epnxil!e
Methuxychlor
T[)xnphen~
PCBIOJ6
PCB 1221
PCB 12J]
PCB 1242
PCB 1248
PCB 1254
PCB 1260
PC[3·1262
PCB-1268
[) (2,'1-)
TP (2,4,5-) (Silvex)
_r~llllletcr Dcs,!iptioll
~-~-
Benzelle
BrolnobclI'l.cne
Butyl benzene (n-)
Sec-butylbenzcnc
TCr1-butyibcnzcne
Chlorob~llzenc
Chlorololucne (2-)
ChlorD10lucne (4-)
Dichlorobenzene (J ,2 .. )
Dichlorobenzene (1,3-)
Dichl(lrohel!z~ne (1,4-)
Pngc J of I I
New Jersey Department of Environmental Protection
N atioJlai Euvironmcntal Laboratury Accreditation Program
ANNUAL CERTIFIED PARAMETER LIST AND CURRENT STATUS
Effective us (If ()7101/2013 unlll 06!30i2014
aboratory Name; OUTREACH LABORATORY Laboratory Number: Ol(OOl Activity ID: NLC130001
11 N ASPEN
,ROKEN ARROW, OK 74012
Itegory: SI·IW07 -Organic Parameters, ChronJatognlph)/MS
Eligihle to
Rcport
allis N.! Datil Stille Code Mnlrb: Trchniqlli; Description Approved Mell.o"
lPiietl No NJ SHW07.04060 NPW GC/MS, P & T or Direct Injection, Capillary [SW-84682608J
lplietl No NJ SHW07.D4065 NPW GC/MS, P & T or Direct Injection, Capill'\IY [SW-346221)0BI
lplicd No NJ SHW07.040fi7 NPW GC/MS, P & T Dr Direct i1JjcctiOll, Capillary [SW·S46816[)8]
lpiittl No NJ SHW07.04070 NPW GCIMS, P & T or Direcllnjcctio!l, Capilhlry [SW-R468260B]
Jplicd Nll NJ SHW07.04071 NPW GC/MS, P & T or Dii"cd 111jcr;lion, Capillmy [SW ·846 8260BJ
lplicd No NJ SI·IWU7.04072 NPW GerMS, P &. T or Direct Injccliol1, Capillary [SW-846826DBj
Jplied No NJ SHW07.0407J NPW GC/MS, P & T or Direct Injection, Capillary rSW-3468?'60B1
Jpli.!d No N.! SHW07.04074 NPW GC/MS, !' & T or Direci InjectioJl, C~pillnry [SW-8468260B]
,plied No NJ SHW07.04075 NPW (ie/MS, P&T, or Dircl:t Injeclion, Capillary [SW ·846 8160q
)plicd No NJ SHW07.04080 NPW GC/MS, P & T or Direci lnjcl!tiun, Capillary (5W-8<168260B]
lplicd Nu NJ SHW07.04081 NPW GC/MS, P & T or Direct Injection, Capi!!nry [SW.84682608]
Jplied No NJ SHW07.()4082 NPW GC/MS, P &. T or Direct injeetion, C,lpiilllJ'Y [SW-0468260B]
,plied No NJ SHW07.04089 NPW GCiMS, P &. T or Direct Injcclion, Capillary [SW-8rI6 R'Z60B]
)plicd No NJ SHW07.04090 NPW GC/MS, P & T [)J' Direct Injeciion, C:JpilhllY [5 W -846 8260BJ
)plied No NJ " SHW07.04095 NPW GC/MS, l' & T Dr Direct injcclioll, Capillary [SW-l),16826GB!
)plicd No NJ SHW07.04100 NPW GC/MS, P 8.: T OJ" Direct Inje'olion, Capilbry (SW ·846 il2.6DBJ
:liiricd Yes NJ SHW07.04120 NPW GC/MS, P &. T DJ" Direel injeclion, Capilla.y (SW-8468260B]
Jplicd N() NJ 51-1W07.04130 NPW GC/MS, P & T or Direct !J~cction, Cnpilinry [SW-S468260BJ
)piicd No NJ 5HW07.04140 NPW GC/MS, P &. T or Direct lnjcctitlJJ, Capilhll;1 [SW·M6 R260BJ
:rtiiicd Yes NJ SHW07.04150 NPW GClMS, P & T or Di,ccllnjcr.tioll, ClIpill;l\:! [SW-846826ll8]
i1plied No NJ SHW07.04160 NPW GC/MS, P & T or Direct Jr~jcr;lioJl Capil1noy ISW ·846 !l260BI
Dplied No NJ SHW()7.04165 NPW GClMS, r & T or Dilcct Injection, Cnpilln.y [SW-R46 826081
pplicd No NJ SHW07.04170 NPW GC/MS, P &. Tor Dircel lnjection, Capilla,y [SW-E<168260[lJ
;lpJi~d No NJ SHW07.04180 NPW GClMS, l' & T or Dir~cllr0ccliol\, C<lpillar: [SW-S'/{) 87.60B}
pplictl No NJ SHW07.01)j 85 NPW GC/MS, P & Tor Dircel Injecli[)JI, Capillury (S W ·846 8260BI
pplictl NlJ NJ Sl-lW07.04186 Ni'W GC/MS, P &. T or Dirccll!l.i~c!ioll, Cnpillnry [S W-846 82608]
pplicd No NJ SHWD7.04187 NPW GC/MS, P & l' or Direct Injection, Cupillary ISW .. 34682608]
pplicd No NJ SHW07NI90 NPW GC/MS, P & T or Direct injection, Capillmy [S \V-8')6 8260131
pplied No NJ SHW07.04100 NPW GClMS, P &. T or Direct InjcctiolJ, Capill:ny [S\V-846826UB1
~11ili'~cl Yes NJ SHW07.042 I 0 NPW GCllvIS, P & T or Direct InjecliOIl, Clpillary [SW-H4682608]
~I'tificd Yes NJ SHW07.0<1120 NPW GC/MS, P & T or Direct iiljcclion, Capill"iY [SW-8468260BJ
pplicd No NJ SHW07.04230 NPW GC/MS, P & T or Direct Injccliun. Capiil,ny [SW-846826GB!
r:y: AE = Air and Emissiuns, 81' = Biologic~1 Tissues, OW = Drinking Waler, NPW~' Non-Potable Wnlcr, SCM = S(llid H1ll1 Chemic,ll M;\lcrinls
.I. _ •••••• 1 ." •• _1; r: ... l D ..... ,,~ ..... , ... ,. J ;,.) I=,.r~rl;"r 0 .' "I' 1l71011?1l1"l IInli! n('1I1l0nl:l
f-'nnuucier Dcscl'iutiOJl
Clhy!bell:lcne
ISlJpmpylbcrJY-cnc
I'rorylbcllzellc (n-)
Toluelh.:
ISDrmpyliDlliGllc (4-)
TrichIOfDOG!IZt:IE; (! .2.,3-)
Trilll<:ll!ylb"nztlli) (1.2,"-)
TrinlclilyibcllI.cllc (l ,3.5-)
T!·iiTlcLhylbc":t.~Jl" (l ,L.l·J
Xy~el)es (tClln!)
Xykll~ (10·)
Xyiene too)
BrolflUC 11101 iJlnctlmnc
UJ"Qn.or.iidliorolodhilllc
Broll1v"lllUJl(:
BI(Jlm,j'ollll
em"bon u:ll11t:hioridc
ClilDtodlHnc
CillorDcLhyi villyl direr (2-)
CblororoJ'l)r
Cilluromc'.ll\ll\e
Di~lloyi ether( Fthyl elher)
Dit:hloropJ'opcnt: (lmns-I ,J-)
L)ibromoch loroll1cthilllc
OibrolllocllJnne (1,2-) (EDEl)
DibrornoiTIclhnne
Clilmm.o·J-chluropropnlle (1,.2·)
Dichiorodilluorolllclbnne
DichloJOu!limw (1,1-i
Didllnroeiha<H: (l,2-)
Dichloroctlicllc ( I, l··j
Dichlomclilcflc (iuJls·1 ,2·)
Png[: ·1 Ilj" I !
New Jersey Department of Environmental Protection
National Environmental L:lboratory Accreditation Program
ANNUAL CERTIFIED PARAMETER LIST AND CURRENT STATUS
Effective :IS of 07/0112013 until 06/3012014
Iboratory Name: OUTREACH LABORATORY Laboratory Number: OKOOI Activity ID: NLC130001
1 N ASPEN
ROKEN ARROW, OK 74012
tcgory: SHWIJ7 -Orgnnic Parameters, Chromntogrnphy/M,s
Eligible to
Report
tllS N.) Datn Stnle Colic Matrix Teclmiqllc Dcscril'tioll Approved l'l'lethod
plkd No NJ SHW07.04235 NPW GClMS, P & Tor Dircclllljec!ioll, Capi1lury [SW-8461l260B.l
plied No NJ SHW07.04240 NPW GC/MS, P & T or Direcllnjcction, Capillary [SW-8468260B]
rlied No NJ SHW07.04241 NPW GC/MS, P & Tor Dirt:cl injection, Cnpillary [SW-84682608J
plit:d No NJ SHW07.04242 NPW GC/MS, P & T or Directlnjectioll, Cupillary [SW-84682608]
rlied No NJ SHW07.04249 NPW GC/MS, P & T or Direct Injection, Cnpillary [SW-8468260BJ
plied No NJ SHW07.04250 NPW GC/MS, P & T or Direct Injection, Copillary [SW-84682608J
pli.:d No NJ SHW07.04270 NPW GC/MS, P & T or Direct Injection, Cnpillary [SW-84682608J
1ifi~d Yes NJ SHW07.04280 NPW GC/MS, P & T Dr Dirl.!ct Injection, Capillmy (SW-84682608]
plied No NJ SHW07.04290 NPW GC/MS, P & T or Direct Injection, Capilhll)' [SW-846 8260B]
plied No NJ SHW07.04300 NPW GC/MS, P & T or Direct Injection, Capillm)' [SW-8468260B]
1i1ied Yes NJ SHW07.043I 0 NPW GC/MS, P & T or Direct il~iection, Capillmy [SW-&46 8260B]
plied No NJ SI-lW07.04320 NPW GC/MS, P & T or Direct Injection, Capillary [SW-8468260B]
plied No NJ SHW07.04322 NPW GC/MS. P & T or Direct Injection, Cupillary [SW-B46 8260BJ
plied No NJ SHW07.04325 NPW GC/MS, P & T Dr Direct Injeclion, Capillary [SW-846 8260B]
plied No NJ SHW07.04327 NPW GC/MS, P & T OJ' Direct Injection, Cnpillnry (SW-846 82608]
liiiieLl Yes NJ SHW07.04330 NPW GC/MS, P & T or Direct Injection, Cnpillnl)l [SW-84682608]
plied No NJ SHW07.04340 NPW GClMS, P & T or Direcllnjection, Capillmy [SW-846 R260B]
plied No NJ SHW07.04350 NPW GC/MS. P & T or Direct Injection, Capillary [SW-8468260BJ
plied No NJ SHW07.04360 NPW GC/MS, P & T or Direct Injection, Capillury [SW-846 8260BJ
plied No NJ SHW07.04365 NPW (iC/MS, P & T or Direct Injection, Cnpillury [SW-8468260B1
plied No NJ SHW07.04370 NPW GC/MS, P & T or Direct Injection, Cnpilbry [SW-846 826DB]
plied No NJ SHW07.04378 NPW GC/MS, P & T or Direct lJ~jection, Capillm)' [SW-846 8260B]
pli.:d No NJ SHW07.04380 NPW GC/MS, P & T or Direct Injection, Capillury [SW-S468260B]
plied No NJ SHW07.04390 NPW Ge/MS, P & T or Direct Il\ieclion, Capillary [SW-8468260B]
11iiicd Yes NJ SHW07.04500 NPW GC/MS, P & T or Direcl Illjeclioll, CnpillUlY [SW-846826DB]
limed Yes NJ SHW07.04530 NPW GC/MS, P & T or Direct Injection, Capillary [SW-8468260B]
plied No NJ SHW07.04540 NPW GC/MS, P & Tor Direcl Injection, Cupillaty [SW-8468260B]
'Plied No NJ SI-lW07.045S0 NPW GC/MS, r & T or Direct .Injcclion, Capillul)' [SW-8468260B]
plied Nn NJ SHW0704560 NPW GC/MS, P & T Dr Dirt!cl Injection, Capilla!)' [SW-8468260B]
plied No NJ SI-lW()7.04570 NPW GC/MS, P & T or Direcl Injection, CnpilhilY [SW-846 82608J
'Plied No N.I SI-!W07.04580 NPW GC/MS. P & T or Direct lnjcctioll, Capilll1lY [SW-84682608]
'Plied No NJ SHW07.0S006 NPW GC/MS, Exlract or Dir lnj, Capillary [SW-84G 8270C]
~Y: AE = Air and Emissions, BT = Biological Tissues, OW = Drinking Waler, NI'W = Non-Pol,lbie Walel', SCM = Solid ami Chemical Malerials
-----.. ~ ... ~ ~ ..... ,. ... 'j ..... .r\ •
Parameter Description
Dichioroelhcne (cis-I ,2-)
Dichloropropnnc (1,2-)
Dichloropropanc ( 1 ,J-)
Dichloropropnnc (2,2-)
Dichloropropene (1,1-)
Dichloroprorene (~is-! ,3-)
Tetrachloroethane (I, 1,2,2-)
TClr.,chloroelhcn~
Trichloroethane (I, 1,1-)
Tric hloroelhane (1,1,2-)
Tricblorocthenc
Trichiorolluorometlm nc
Tlichloro (1,1,2-) tlinuoroeti1nnc (1.2,2-)
Trichloropropune (1,2,3-)
Vinyl acetale
Vinyl chloride
Act;tonc
Curboll disuilidc
Butnnone (2-)
Etbylncetale
Hexilnonc (2-)
N-Nitroso-di-n-bulyimninc
Pcnt~none (lJ-methyl-2-) (MIBK)
M cthyllert-butyl ether
Hcxtlchlorobu!ndienc (1,3-)
Hcxuehloroethnne
Nuphthalene
Styrene
·1 etr<lchIDroctimnt: ( I ,I, I ,2-)
TrichlDrobenzene (1,2,4-)
Niil'obcJlzCllc
N-N i troso·J i-I,,,propybll1 i lie
Pm~e 5 or I I
New Jersey Department of Environmental I>rotcctioll
National Environmental Lllboratory Accreditation Program
ANNUAL CERTIFIED PARAMETER LIST AND CURRENT STATUS
Effective liS of 07/01il013 until 06/30/:2014
aboratory Name: OUTREACH LABORATORY LaboJ":ltory Number: OK001 Activity ID: NLC130001
11 N ASPEN
..ROKEN ARROW, OK 74012
ltcgory: .51·1W07 --Organic Parameters, Chtomatograph)fMS
Eligible to
Report
IItOIS N,! Dntn Stllte Code Matrix Technique Description Appruved Mdhod
lplicd No NJ SI-1W07.D5010 NPW GClMS, Extract or Oi .. lr\j, CnlJilimy [SW-846 H270q
lplied No NJ SHWD7.05030 NPW GCiMS, Extrac:l or Dir 11lj, C<lpillal), [SW-84G 827DC]
Jplied No NJ SHW07.05038 NPW GC/MS, blrJct Of Dir liti, Capillary [SW-346 ~270Cj
Jplicd No NJ SHW07.05040 NI'W GC/MS, Extract or Oif Inj, Capillmy [SW-8468270C]
Jplicd No NJ SI-IW07.05048 NPW GC/MS, EX.IT~ICI or Oi,. lnj, Cnpillnty [SW-846 8270C]
lplied No N.l SHW07.0505D NPW GClMS, EXII1lCI or Dir Inj, Cnl)illurJ [SW-346 S:270C]
lplicd No NJ SHW07.05060 NPW GC/MS, EXlract 01' Dir Inj, Cnpillmy [SW-84b 827DC]
]plied No NJ SHW07.05062 NPW (ie/MS, E,lmct or Dir Inj, Capillary [SW ·846 8270C]
Jplicd No NJ 51-1W07.05063 NPW GClMS, Exlrdcl OJ' Oil Illj, Cupillary [SW-R468270q
Jplied No N.l SHW07.05070 NPW GUMS, Extr.lel or Dir Iqj, Cnpill:ny [SW-8468270q
'l1illcd Yes NJ SI-IWO'I,05080 NPW Ge/MS., E.~tl<1Ct or Oir In.1, Cnpill;l1), [SW-8,16 8270C]
lplicd Nt) NJ SHW07.05090 NPW GCiMS, E:xtrnct or Oir JIlj, CnpillulY [3W-8468270C]
lplicd No NJ SI-IW07.05100 NPW GClMS, EXIf<1cl or Dir !nj, C:lpillui'Y [SW-S4f) B27fJC]
lpli(:d No NJ SHW07.05110 NPW GC/MS, ExIiDel OJ' Dir inj, C~pi!l~ry [SW -846 8270C]
lplicd No NJ SHW07.05115 NPW GCIl'I'IS, Extl<lct 01' Dir Inj, C~pillnl)' [SW.·S4682.70Cj
lJllicd No NJ SHWO'I.05120 NPW (iC/MS, Ext>1!Cl or Oir Inj, CapiHm)' [SW-846 ~270C]
lplicd No NJ SHW07.0S130 NPW GC/MS, EXtl<1ci or Dir h~j, Cnpilimy [SW-846 8270C]
Jplietl No NJ SHW07.051J2 NPW GC/MS, Extrilcl or Di!" In,i. Capillary [SW-846 R270q
lplicd No NJ SHW07.05140 NPW GC/MS, Extraci or Ojr Inj, Capillary (SW··8468270Cj
Jplicd No NJ SHW07.051S0 NPW GC/MS, Extmct or Dir h\j, C"pillary [SW.·S46 827UCj
lplied No NJ SHW07.DS160 NI'W GC/MS, Exlracl oj' Dir lnj, Capillary [S\V-846 SDOC]
:Itificd Yes N.J SHW07.05170 NP'vV GClMS, EX.WICI. or Dir Inj, Capiilmy [SW-R468270C]
rplicd No NJ SHW07.05180 NI'W GC/MS, Exlract Dr DiT In.!, CU[lill:1lY [5W-846 R2.70C]
flplicd No NJ SliWD7.05190 NI'W GC/MS, Extmct or Dir inj, Capi!!my [SW·R46 S27liC]
['plied No NJ SHW07.05200 NPW GC/MS, Exlra(;l or DiJ' h,j, Capillary [SW-846827DC]
pplicd No NJ SHW07.05210 NPW GCrMS, Extracl or nir inj, Curillmy [SW-8,j6 S270C]
pplicd No NJ SHW07.05220 NPW Ge/MS, Exlrncl or Dir Inj, C;;piliary [SW-H4687.70Cj
pplicd ND NJ SHW07.05230 NPW GC/MS, Exli;\C[ Dr Oir Inj, Capillary [5'{;-846 S2lDCI
pplicd No NJ SHW07.05240 NPW GC/MS, Exlra(;l Of' Oir h~, CapilhH)' [S\V-8468270Cj
pplicd No NJ SHW07.05250 NPW GUMS, E.xlmcl or Dir Irti, Cupiliary [SW-8468270Cj
pplicd No N.I SI-IW07.05260 NPW GC/MS, Extract or Oir Illj. CapiHalY [SW-H<l68TiDC]
ppli(~d No NJ SHW07.05270 NPW GC/MS, Extraet Do· Dir Inj, Capil];w>, [SV!-R<\68270Cj
EY: AE = Aif and (:missiolls, BT = Biologic"1 Tissues, OW = Drinking Watcl'. NPW = Non-Pnl;,blc Waler, SCM = Solid nlld C!lelllic"l Materials
• .,j " .:r-'ll, .,-.... t r:-n:".,:,,, •. ,,· .... r 117Jn I /''In 11. I1:-1J;I OflJlrV71l r J.
--
--------------
Pllrllno~tcr Dcscr~,tion
N-N i trawl! iphcnyl "111 ine
Curbazoie
BCl1'l.idine
Dich(orobcfnidi!lc (J,3'-)
Af,iliJic
ChlorCIllnilinc (4,·)
NitroJnilinc (2-)
Nilrilnnilinc (3 ·)
Nitro,lI1iiinc ('i-J
Chlol"(')Jmphlilalcne (2-)
Hexlichlorobclfzcne
l·b:lIchiorobulmJicne (i ,:1-)
1·]cxr;ch!oI'DcyciDpcntndienc
j icxn~h!orocllinlll
H<:X;lChlo[\)Pf opcnc
Trichlorobellzcllc (1,2,4-)
Bis (2-r,hloro~lhoxy) lTIctlmnc
f3is (2-C!!I010Glhy!) ether
8is (2-chloroisopropyl) ether
Chinmphc!lyl 'pMnyl ether (4-)
Br()inOpIJl;l~yl-phcIlY! ether (4-)
Dinitrololtlcne (2,4-)
Dinitfl)[ohwnc (2,6-)
lsnpholt~n(:
NiloobcflZ,"IC
Butyl u(;!:1.),1 plllhniaic
Rio; (2-cthylhc:xYL) phtll\dulC
Didhyi phtimiilk
D1!!lC~hy[ pht!J:l!nte
Oi··,,·bmyl phth"11ll~
Di ·,,·oclY! p!1illahl~
l\ci;l1nphthc!1(:
Page 6 Dr J I
New Jersey Depar tment of Environmental Protection
National Environmental Laboratory Accreditation Program
ANNUAL CERTIFIED PARAMETER LIST AND CURRENT STATUS
Erfcctiyc as of 07101/2013 unlil 06/3012014
Iboratory Name: OllTREACH LABORATOHY Laboratory Number: OKOOI Activity ID: NLC130001
1 N ASPEN
~OKEN ARROW, OK 74012
tcgory: SHW07 -Organic PurllOiclers, Cltromalogrnph)/MS
Eligible to
J{cPOri
IllS N.' Dlliu Slate Code Mulrix Tcchnilillc Description Approved Method
llicd No NJ SHW07.05280 NPW GC/MS, Exlrncl 01' Oil' lnj, Capillary [SW-B468270C]
,Iil!d No NJ SHW()7.0529D NPW Gc/MS, EXlmct Dr Oir Inj, CnpillUl)' [SW-846 B270Cj
}Iied Nil NJ SHW07.05300 NPW GC/MS, Exlracl Dr Oil' lnj, Capillary [SW-8468270e]
llied No NJ SHW07.05310 NPW GC/MS, Exlrncl or Oil' Inj, Cupillnry [SW-846 8270C]
lliL:d No NJ SHW()7.05320 NPW GC/MS, Exll~ICl or Oil' Inj, Cupillflry [SW-846 B270Cj
1lit:d No NJ SHW07.0S330 NPW GC/MS, Exlract or Oir inj, Capillary [SW-8468270q
Jlied No NJ SIIW07.05340 NPW GC/MS, Exlr..'ct or Oil' Inj, Capilhlry [SW-8468270C]
llicd No NJ SHW07.05J50 NPW GC/MS, E.xtmcl or Oir Inj, CupiltlllY (SW-8468270C]
Jlied No NJ SHW07.05360 NPW GC/MS, Exlmcl or Oil' Inj, Capillary [SW-8463270C]
Dlied No NJ SHW07.05370 NPW GC/MS, EXlr:JCl or Oir Inj, Cnpilll1l)' [SW-8468270C]
plied No NJ SI-lW07.05380 NPW GC/MS, Extr,lct or Oir !nj, Capillary [SW-M68270e)
plied No NJ SI-IW07.05390 NPW GC/MS, Exlrnct or Oil' Inj, C;lpillmy [SW8468270C]
i1liccl No NJ SHW07.05410 NPW GC/MS, EXlmcl OJ' Oil' liti, C~pjllnlY [SW-846 S270C)
plied No NJ SHW07.05420 NPW GC/MS, tXlr.1Cl or Oil' Inj, Capillary [SW-8468270C]
pli<:d No NJ SHW07.05430 NPW GC/MS, Exlracl or Oir Inj, Cnpillnry [SW-8468270C]
plied No NJ SI-IW07.05440 NPW GC/MS, Extracl or Dir Inj, Cnpillill)' [SW -846 8270e]
plied No NJ SHW07.05450 NPW GC/MS, Exlracl or Dli' Inj, Cnpilhlry [SW-B46 8270C]
plied No NJ SHW07.05460 NPW GC/MS, Exlmct or Dil' Ioj, Capillal}' [SW·846 8270e]
plicd No NJ SHW07.05470 NPW GC/MS, E.~lmct or Oir Inj, Capillnrj [SW-8468270C)
plied No NJ SHW07.05480 NPW GC/MS, Exll1lct or Dir Inj, Capillary [SW-8468270C]
[llied No NJ SHW07.05490 NPW GClMS, Exlmcl or Dir Inj, Capillary [SW-il<l68270q
'1ificd Yes NJ SHW07.05500 NPW GC/MS, EXlracl or Oir Inj, CapillUl)' [SW-8468270e]
:tillcd Y~s NJ SHW07.05510 NPW GC/MS, Exlmcl OJ' Oil' Inj, Capi!lnry [SW-846 8270C]
plied No NJ SHW07.05520 NPW GC/MS, Extl1lct Dr Oil' Inj, Capillmy [SW-S46827OC]
plied No NJ 5HW07.05530 NPW GC/MS, Exll1lCl or Dil' IJti, Capillary [SW-8468270q
:tilied Yes NJ SHW07.05540 NPW GC/MS, Exlrnci or Oil' Inj, Capillal}' [SW-8468270C]
plied No NJ SHW07.05550 NPW GC/MS, Extnlcl or Oil' l!1j, Capillnry [SW-H468270C]
:tilied Yes NJ SHW07.05560 NPW GC/MS, Exlracl or Dir Inj, Capilim), [SW-8468270C]
:tilled Yes NJ SI-IW07.05570 NPW GC/MS, Exlmct or Dir lnj, CapillulY [SW-8468270C]
:tiiied Yes NJ SHW07.05590 NPW GC/MS, Extract or Dir llti, Cupiflnry (SW-8468270C]
plied No NJ SIIW07.05600 NPW GC/MS, ExlnlCI or Dir Inj, Capilimy [SW-8468270C]
plied Nil NJ SHW()7.05(,91 NPW GC/MS, EXll1lcl or Oir Inj, Capillary [SW-846 8270C]
Y AE = Air and Emissions, BT = Biological Tissues, OW = Olinking WaleI', NPW = Non-Polable Wnler, SCM = Solid nnd Chemical Malerials
--. -.. ~ ,..,... " J. A-,,,) 1 P'1"I., ... _.:1 f\J'./")f)l'l"i.1
I'llrarnctcl' [)cscr'p_~_
Anlhr']ccnc
Acenaphlhyicnc
Bcn'l.O(n)nnlhrncene
Benzo(n)pyrcnc
Benl-o(b)l1uornllliJt:llc
Benzo( ghi)pclylcnc
8enzo( k)lluDrnnlilcnc
Chryst!llc
Dihellzo(a,ll)nnlhmcenc
FluolUnlhene
Fluorem:
I ndcno( I ,2,:l-cd)pyrcnc
Nnphlhnlcnc
Phenanlhrene
Pyrene
Methyl phenol (4-chloro-3-)
Chlorophenol (2-)
Dichlorophcnoi (2,4-)
DimelhylphclIol (2,4-)
Dinilrophenol (2,4-)
Dinilrophellol (2-melhyl-4,6-)
Mclhylphellol (2-)
MClhy!phenol (<1-)
Nilrophcrlol (2-)
Nilrophcnol (4-)
Pentachlorophenol
Phenol
Trich!oi'DpiJcnol (2,4,5-)
Trichiorophenol (2,4,6-)
MelhylJlhcnol (3-)
Dihcnzoltmm
Dichlor{)hcll'l~n<! (! ,2 .. )
Pal!e 7 or 11
New Sersey Department of Environmcntall'rotectioll
National Environmcnt:il Laboratory Accreditation Program
ANNUAL CERTIFIED PARAMETER LIST AND CURRENT ST ATOS
Effective noS of 07/0112013 until OMJO/2014
,aboratory Name: OliTREACH LABORATORY Laboratory Number: OKOOl Activity lD; NLC130001
1] N ASPEN
:ROKEN ARROW, OK 74012
ategory:
htll:>
crtiJicd
C11iIicd
crtitlcd
CItified
crtified
cltiJicd
CItified
Citified
crlilicd
crtillcd
cl1i[icu
cI1iiicd
crtilicd
crlil1cd
c11iJ'ieu
crlificd
No NJ
No NJ
No NJ
No NJ
No NJ
Yes NJ
S
S
S
S
S
S
_____ A-'..f'provc
i Method
[SW-846327fJC]
[SW -846 S2.70C]
(SW-8468270C]
[SW-8468270D]
[SW-846 8270D]
[SW-8468270Cj
____ f_'nramctcr O~scriptjon
Dichlol obenzenc ( 1,3-)
Dichlllrobt~llzt:nc (i ,'r-)
BcnziJit: acid
DecalJe (n·)
()cladc~nllc (n·)
Pyridine
WPP09 -RndiochclIl.: Radiollctivit)' 1 RmJioJlllclilie
Eligihle to
Report
N,/ Duhl Slate Code 1\'lnt.r;Y ___ -'-_____ ~chnilJllC Description Approved MellJod__ Pnrnrnclel" flescriIll;oll
Yes NJ WPP09.0 I 000 NF'W Proporlional 1)1" Scil1lill~lilJll [EPA 900.0] Gross ~Iphn
Ves NJ WPP09.03000 NPW PJOporlirllJal Counlcr [EPA 900.0] OIO.IS bela
Yes NJ WPP09.03100 NPW Gamma SpeClmlTtClry [EPA 90!. J 1 CesiUll1 j :)'1/1 J I
Yes NJ WPP09.03200 NPW GUIlltt1a Spectromctry (EPA 901, I j C:)hHit 60
Yes NJ WPP09.03300 NPW Gamma SpcctromClty (EPA 901.1] Zinc 65
Yes NJ WPP09.05000 NPW Precipilalion iSM 7S00-J~;i BJ Radil!1l1 -lOin;
Yes NJ WPP09.06000 NI'W R'ldiochcmiCltJ [SM 7500-Ru B] Rndiuln -nG
Yes NJ WPP09.06020 NPW Co-Precipilalion / Bela Counling [EP A 'lOti.D) RHUiuJl1 .. 22g
Yes N.l WPP09.07000 NPW Gamma Speclrometry [EPA 90i.l] Pholon Emitters
Yes NJ WPP09.08000 NPW Prccipltalion Bela COllniing [EPA 905Jl] Stronliull1-89. 1)0
Yes NJ WPP09.0S I 00 NPW Precipitation Bela Counting [EPA 905.01 Slmntiulli -90
Yes NJ WPP09.09000 NPW Co-Prcr.ipit<lli(J1l 1 Alpha COlJllting [USER DEFINED ASTM 0517'P) i I UJ"i\i1iul1l
No NJ WPP09.090 I 0 NPW Isotopic Atlnly5i~! Alpha SpcctrolllclIY [ASTM D 3l)72] tir'lIlium
Yes NJ WPP09.09020 NPW Laser PhospiJorilflclry [ASTM D51741 UI>:niulIi
Yes NJ WPP09. 10000 NPW Distillalion/Liquid Scinlillation (EPA 906.0] Triliull1
Yes NJ WPP09.11000 NPW Rudiochclllicnl/ Alpha Coullting (EPA 907.0] PIULOiliHlJ1
.E\': At::: ~ Air fond EmissioJ1s, 8T = Biologic;!1 Tissucs, DW ~ DrinkiJ!g \V"ier, Nl'Vi~' NOll-Potable Wale!", SCM = So!ir! flnd Chcmicai /viat<:ri,lis
t" fIo:~":'\·M .} ••.• 1:; !".. .. /H'll'1nl rl
#~CO<;-4I~
~ I:
P:lgC 8 oi-: !
New .Jersey Department of Elivironmental Protection
Nll tioll:l) Environment:.) Laboratory AccreditlitiolJ Progralll
ANNUAL CERTIFIED PARAMETER LIST AND CURRENT STATUS
Effective ns of 07/0112013 until 06/30/2014
aborntory Name: OUTREACH LABORATORY Laboratory Number; OKOOI Activity 10: NLC130001
[1 N ASPEN
ROKEN ARROW, OK 74012
tcgury; WPPIO -Radon ill Wastewater
Eligible to
Report
Itll5 NJ Data Stnte Code Mlltrix Technique Description Approvct! Method
rtilled Yes NJ Wpp 10.0 I 000 NpW Liqlliu Scinlillntion [USER DEFINED SM 7500]
tegor),: SHWf)2 -Chu"ncteristics of BU'lllrdons Wnstc
Eligible to
Report
ttns NJ Dnta Slate Code Mulrix Technique Descriptio'l Approvell Method
Itilieu Yes NJ SHW02.01000 NPW, SCM Pcnsky M;Hlcns [SW-846 1010]
,tilled Yes NJ SI-IW02.03000 NPW, SCM Aqueolls Waste, Potentiometric [SW-M69040B]
Itificd Yes NJ SHW02_06900 NPW, SCM TCLp, To.xi<:ily Procedure, ZHE (SW-S41i [J II J
Itilleu Yes NJ SHW02.07000 NPW,SCM TCLP, Toxicity Proccc1me, Shnk(;r [SW-846 1311]
rlificd Yes NJ SHW02.08000 NPW, SCM Synthetic prr Leachate Procedure [S W-846 iJ 121
Itcgory: StlWII4 -Inorganic I'nrllmeter~
Eligihle to
Report
llliS NJ Dutu Stnte Code Matrix TecJ'lIi~scripliol\ ·\'pproycd Method
rtilled Yes NJ SHW04.0J700 NpW, SCM Chromium VI Digestion [SW·S'16 J060A)
Ililied Yes NJ SHW04.05000 NPW, SCM lCP [SW·84660108J
Itilled Yes NJ SHW04.06500 NpW,SCM iep [SW-8466010B]
,tilled Yes NJ SHW04.0lJ()OO NpW, SCM ICP [SW-846601013]
Itilled Yes NJ SHW04.11500 NpW, SCM ;CP [SW-846 60 I DB]
rtilled Yes NJ SHW04.13500 NPW,SCM ICp [SW-B46 60 I DB]
Itilied Yes N.I SHW04.15100 NPW,SCM lep [SW-8466010BJ
Itillcd Yes NJ SHW()4.15500 NpW, SCM iCP [SW-S466010B]
rtilied Yes NJ SHW04. I 7500 NPW, SCM ICP [SW-84660108]
,tilieu Yes N.I SHW04.18500 NPW, SCM ICP [SW-8466010B]
Itillcu Yes NJ SHW04.21000 NPW, SCM C[Jlo,.jml:tri~ [SW-8467196A]
rtiried Yc:s NJ SHW04.22500 NPW, SCM lCP [SW-8466010B]
,tificu Yes NJ SHW04.27S00 NPW, SCM lep [SW-846 60 t OB]
IlilieLl Yes NJ SHW04.30500 NpW, SCM ICP [SW-846 (,0108]
,tilied Yes NJ SHW04.3 i 500 NPW, SCM Icr [SW-841i AOIOB]
:Y: AE = Air tll1d Emissions, BT = Biologicai Tissues, DW = Drinking Water, NPW = Non· Ppwble W:lier, SCM = Solid unci Chemicnl Mnleriu\s
.""~.' •• -, .• '" ,"","'·n,..., .. ,.
3!\f.vJ~:~
;>v \~
• J
Parameter Oc~cri.ptiol\
Radun
Pnnunctcr l>cscripti,:!!
i!;uitability
Corros;vity -pH wnsle, >20% w:licr
Volat i!c organics
Metais
IV! t:wls -l>rga:lics
Parameter Description ------Mel,\ls
Aluminum
Anlimnny
/\locnic
Barium
Bc.yllil!1Il
BOI"011
Cmhnin~n
Cnlcium
Chromium
Chromium (V!)
Cobnlt
Leau
Magn..:siun,
Manganese
Pn;'" q or 11
New Jersey Departmcn t of Ellviromnell tal Protection
National Environmental Laboratory Accrcditation Program
ANNUAL CERTIFIED PARAMETER LIST AND CURRENT STATUS
Effective as of 07f01120/3 HUH! 06/30f20/4
abOl'atory Name: OUTREACH LABORATORY Laboratory Number: OKOOI Activity ID: NLC130001
11 N ASPEN
ROKEN ARROW, OK 74012
-----------------------------------------------------------------------------------------------
ltcgury: SHW04 -Inorganic PJ\rlIIllClcrs
Eligiule to
Report
alus NJ Onla Stale Codc
:ttificd Yes NJ SHW04.34000
:rtificd Yes NJ Sl-IW04.35500
:l1ificd Yes NJ SHW04.J9000
:nilicd Yes NJ SJ-lW04.41000
:rtified Yes NJ SHW04.43000
:Iti!icu Yes N.1 SHW04.44000
:Itilicd Yes NJ SHW04.45000
:J1ified Yes NJ SHW04.47500
:rtilicd Yes NJ SHW()4.49000
ntego.-),: SHWO!) -Miscc\lIlIlC(JUS l)a)"(Ullclcrs
Eligiule 10
Reporl
alliS N,) (hIll Slllle COlic
pplied No NJ SHW09.02000
liP lieu No NJ S HW09.04 100
utcgul'Y: SIIW04 -Inorgllnic Pal'1llllctcrs
Eligihlc to
Report
alliS N.' Ollta Slate Codc
mtilieu Yes NJ Sl-IW()4.03000
~ttified Yes NJ SHW04.24500
cltilkll Yes NJ SHW04.26000
cI1ilied Ycs NJ SHW04.33500
Cl1iflcd Ycs NJ SHW04.33000
Mntrix Tech niqnc 1)~~,:.iJlI!l)H /'.lolU'm"~1 Met hod
NPW, SCM ICP (SW-846 60 lOB]
NPW,SCM ICP [S\V-846 60 lOB]
NPW. SCM ICP [SW,3466010B]
NPW, SCM ICP [SW-846 60 lOB]
NPW, SCM ICP [SW-8466010BJ
NPW,SCM ICP [SW-8466010B]
NPW, SCM lCr [SW-846 60108]
NPW,SCM ICP [SW-84660WBl
NPW, SCM ICP [5W-8466010B]
Mnlrix Tct ll ""II C O~;~,'l'lion "!I,.(ro'.·1!ti (\,IclhlJd_
NPW. SCM Dislilbliol1 [SW-8469010q
NPW, SCM Titrilllctric/Manual Spectrophotollletric [SW-8469014]
Mntri:-; Tcdlfli<:'IC DcscriiJ' 10: ,. Ap~ ~~v~tl Method
SCM Acid Digestion, Soil Sediment & Sludge [SW ·846 30508]
SCM ICP [5W-346 60 IOBj
SCM ICP [SW-R46 60 I 08]
SCM AA, i'vImlUul Cold Vapur [SW-846747IA]
SCM ICP [SW-846 (,0)081
EY: AI': = Air and Emis5ion5, BT = Biological Tissues, OW = Drinking Wall:r. NPW = Non-Potable WaleI', SCM _. Solid and ChcnoicallVLHcrinls
,-" .... 1..-.. I VH. '" _ •• :1 n .r.I':'/'H"'1 ,I
~~TJRI!CO~\
Parnlllctc,' Dcstril :'''\1
MDlybdcnulH
Nickel
Selcniu111
Silver
Sodium
Strontiu1l1
Thallium
Vnll~dilOlI\
Zinc
I'nl'nmc!ct· "' • .n: ·',..,I'_ti_Ol_l _______ .
Cyanide
Cyanide
1~llmclcr Dcscri~1II
MCiols
Cupper
Iron
l'vJCJCUJ1' . solid wn~lc
Potassium
lJnge lO of \1
New Jersey Department M Environmcntall'rotcctiOIl
National Environmental Laboratory Accre<iitMion Program
ANNUAL CERTIFIED PARAMETER LIST AND CURRENT STATUS
Effcctivcns of 07JOI/2013 until 06/]012014
lboratory Name: OUTREACH LABORATORY Lahoratory Number: OKOOI Activity ID: NLC130001
1 N ASPEN
ROKEN ARROW, OK 74012
tegory: SHWI\S -Orgllilie Pllrnmt,tcrs, Prep. I Scrcening
Eligible to
Ihport
tllS N.! DI.tit SUIte Code Mlltrix ___ Tl!chniCJl1t! DCSCl'ipiioll "'rrrovcd Method
plied No NJ SJ-IW05.05000 SCM Ullr'lsonic Extl11clion [SW 846355013]
:1ilicd Yes NJ SHW()5.1 :WOO SCM Cle'lnup-Fiorisil [SW ·846 3620B]
:iilied yc~ NJ SHW05.17000 SCM Cbll1up-Sulli.l!'ic Acid/KMn04 [SW-B46 J6G5Aj
tegory: SHW()9 -Miscellaneous Pllrameters
Eligihle 10
Reporl
. rJ' 1\ Et:or." ~~-"~ '<!'l -< ~
l'urnJ!!~"r I2.c,~triptj"l1
Semivolnlilc ur~:.nics
Selllivol~i!!~ organics
Scmivoialile oJ'ganics
~ N.I Dllla Slate Ct,de Matrix Tccitniql'c Desc!~(llioll Approved Method ____ ~11l'nltlCfCr Descriptioll
.tilied Yes NJ SHWOl),6(]OOO SCM Propol1ional Counler [SW-84693IO] Gras:i -nJphu-belii
Ili/ied Yes NJ SI-1W()9.60105 SCM Radon LOmmwtion [DOE Ra-O'fJ Radium ·126
rtified Yes NJ SHW09.60106 SCM Prceipilnlioll [SM 7500-Ra 8] Rndium -226
ttificd Yes NJ SHW09,60111l SCM Prccipi!nlion [5W-846 9310J )("diulll -22H
llificd Yes NJ SHW09.60 120 SCM Gamma Speclrolllclly [DOE 4.5.2 3J Cesium I 34J 13-;
rtillecl Yes NJ SHW09.601]O SCM Gammu Speclramclly [DOE 4,5.23] Coonh 60
rtificd Yes NJ SHWOC),60140 SCM G'llnmn SpcclromClJ)' [DOE 4,5_2_3] Zin~ 65
I'li/jed Yes NJ SHW09,GO 150 SCM Gamma Spcclrolnt:l!y [DOE 4.5.2.3] Barium I:J3
Itified Yes NJ SHWOC),60160 SCM Gamma SpcctromcllY [DOE 4.5.2.3] [USER DEFINED l-lASL Pholon Emillers
Ga-Ol-Rl
l1i/icd Yes NJ SI-IW09_60200 SCM PreClpltalion Bela Counting [DOE S1'-O J , S1'-02] Siroulium -89, 90
,-tilied Yes NJ SI-IW09_60300 SCM FluommellY [ASTM D 5174] UrnniuJr.
11illcd Yes NJ SHW09_60310 SCM Alpha Spcclrom<:t.y [DOE U-ill1 Ul'tl!liuln
11illed Yes NJ SHW09.60400 SCM Alpha Spcclrometr;' [DOE 4.5.5] [OTHER L\NL ER .. 7.00j ThorilJln
~~
F. AieJJo, Manager
~'\': AE = Air and Emissions. BT = Biologica! Tissues, [lW = Drinking Wal~r, NPW Non-PDluhlc WaleI', SCM = Solid and (,he:nical M~lc,.ials
I lfl
LABORATORY
ACCREDITATION
BUREAU Certificate # L2284
Scope of Accreditation
For
Outreach Technologies, Inc.
d.b.a. Outreach Laboratory
311 N Aspen Avenue
Broken Arrow, OK 74012
Donna Eidson
918-251-2515
In recognition of a successful assessment to ISO/IEC 17025:2005 and the requirements of the DoD
Environmental Laboratory Accreditation Program (DoD ELAP) as detailed in the DoD Quality Systems
Manual for Environmental Laboratories (DoD QSM v4.2) based on the National Environmental
Laboratory Accreditation Conference Chapter 5 Quality Systems Standard (NELAC Voted Revision
June 5, 2003), accreditation is granted to Outreach Laboratory to perform the following tests:
Accreditation granted through: March 24, 2014
Testing -Environmental
Non-Potable Water
Technology Method Analyte
Gas Proportional Counting EPA 900 1 9310 Gross Alpha
Gas PmpOliional Counting EPA 900 19310 Gross Beta
Gas Proportional Counting EPA 904 1 9320 Radium 228
Gas Proportional Counting EPA 90S Strontium 89/90
Gas Proportional Counting EPA 90S Strontium 90
Liquid Scintillation Counting EPA 906 Tritium
Liquid Scintillation Counting EPA C-01 Carbon-14
Liquid Scintillation Counting DOE HASL TC-O 1 Technetium 99
Gas Proportional Counting SM7500-RaB Radium 226
Gas Proportional Counting SM 7500-RaB Total Radium
Liquid Scintillation Counting SM 7S00-RnB Radon 222
Alpha-Spec EPA 907 Modified Am-241
Alpha-Spec EPA 907 Modified Am-242/243
Alpha-Spec EPA 907 Modified Cm-242
Alpha-Spec EPA 907 Modified Cm-243 1244
Alpha-~pec EPA 907 Modified Cm-244
Alpha-Spec EPA 907 Modified Cm-24S/246
Alpha-Spec EPA 907 Modified Np-237
AI~ha-S~ec DOE HASL 300 Po-2 RC Po-21O
Alpha-Spec EPA 907 Modified Pu-238
Alpha-Spec EPA 907 Modified Pu-239
Alpha-Spec EPA 907 Modified Pu-239/240
Al2ha-SEec SM 7S00Ra B Modified Ra-226
Alpha-Spec LANL ER 200 Modified Th-227
Alpha-Spec LANL ER 200 Modified Th-228
Form 403.8-Rev 1-4-11-11 Page I of 15
LABORATORY
ACCREDITATION
BUREAU
Non-Potable Water
Technology
Alpha-Spec
Alpha-Spec
Alpha-Spec
Alpha-Spec
Alpha-Spec
Alpha-Spec
Alpha-Spec
KPA
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Fonn 403.8-Rev 1-4-11-11
Method
LANL ER 200 Modified
LANL ER 200 Modified
ASTMD3972
ASTMD3972
ASTMD3972
ASTMD3972
ASTMD3972
ASTMD5174
EPA 901.1
HASL 300 Ga-01-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-01-R
DOE 4.S.2.3
EPA 901.1
HASL 300 Ga-01-R
DOE4.S.2.3
EPA 901.1
HASL 300 Ga-01-R
DOE4.S.2.3
EPA 901.1
HASL 300 Ga-01-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE4.S.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE4.S.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-01-R
DOE4.S.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE4.S.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.S.2.3
EPA 901.1
HASL 300 Ga-01-R
DOE 4.5.2.3
Certificate # L2284
Analyte
Th-230
Th-232
U-233/234
U-234
U-235
U-235/236
U-238
Uranium, Total
Ac-227
Ac-228
Ag-108m
Ag-110m
Al-26
Am-241
Am-243
As-72
As-73
As-74
Ba-133
Ba-140
Be-7
Page 2 of 15
LABORATORY
ACCREDITATION
BUREAU
Non-Potable Water
Technology
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Fonn 403.8 -Rev I -4-11-11
Method
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
Certificate # L2284
Analyte
Bi-211
Bi-212
Bi-214
Br-76
Br-77
Br-82
Cd-l09
Ce-139
Ce-141
Ce-144
Cf-249
Cf-251
Cl-39
Cm-243
Co-56
Co-57
Page 3 of 15
I
LABORATORY
ACCREDITATION
BUREAU
Non-Potable Water
Technology
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Fonn 403.8 -Rev I -4-11-11
Method
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-01-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-O l-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-O l-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
EML4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-O l-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE4.S.2.3
Certificate # L2284
Analyte
Co-58
Co-60
Cr-51
Cs-134
Cs-135
Cs-136
Cs-137
Eu-152
Eu-154
Eu-155
Fe-59
Gd-153
Ge-68
Hf-181
Hg-197m
Hg-203
Page 4 of 15
LABORATORY
ACCREDITATION
BUREAU
Non-Potable Water
Technolo2Y
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Fonn 403.8 -Rev I -4-11-11
Method
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3-R
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 90l.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901 .1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 90l.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
00E4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
00E4.5.2.3
Certificate # L2284
Analyte
1-131
Ir-192
K-40
Kr-85
La-140
Mn-54
Na-22
Na-24
Nb-94
Nb-95
Nd-147
Np-236
Np-237
Np-239
Os-191
Pa-231 I
Page 5 of 15
LABORATORY
ACCREDITATION
BUREAU
Non-Potable Water
Technoloey
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Fonn 403.8 -Rev I -4-11-11
Method
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE4.S.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE4.S.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE4.S.2.3
EPA 901.1
HASL 300 Ga-O l-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
Certificate # L2284
Analyte
Pa-234m
Pb-210
Pb-211
Pb-212
Pb-214
Pm-144
Pm-146
Po-209
Ra-223
Ra-224
Ra-226
Ra-228
Rb-83
Rb-86
Rh-101
Rh-106
Page 6 of 15
LABORATORY
ACCREDITATION
BUREAU
Non-Potable Water
Technology
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Fonn 403.8 -Rev I -4-1\-11
Method
EPA 90l.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 90l.1
HASL 300 Ga-O 1-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 90l.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 90l.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 90l.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 90l.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 90l.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 90l.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 90l.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 90l.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-01-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
Certificate # L2284
Analyte
Ru-l03
Ru-l06
Sb-124
Sb-125
Sc-46
Se-75
Sn-113
Sn-126
Sr-85
Ta-182
Tb-160
Th-227
Th-228
Th-230
Th-231
Th-232
Page 7 of l5
LABORATORY
ACCREDITATION
BUREAU
Non-Potable Water
Technology
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
ICP
rcp
rcp
rcp
rcp
rcp
rcp
rcp
rcp
rcp
rcp
rcp
rcp
rcp
rcp
rcp
rcp
rcp
ICP
ICP
rcp
ICP
rcp
ICP
ICP
rcp
ICP
Fonn 403.8-Rev 1-4-11-11
Method
EPA 901.1
HASL 300 Ga-01-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-01-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-01-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-01-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-01-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-O 1-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-01-R
DOE 4.5.2.3
EPA6010B
EPA 6010B
EPA 60 lOB
EPA 6010B
EPA 6010B
EPA 6010B
EPA 6010B
EPA 60lOB
EPA 60lOB
EPA 60lOB
EPA 6010B
EPA 6010B
EPA 6010B
EPA 6010B
EPA 6010B
EPA 60lOB
EPA 60lOB
EPA 6010B
EPA 6010B
EPA 6010B
EPA 60lOB
EPA 60 lOB
EPA 6010B
EPA 6010B
EPA 6010B
EPA 60 lOB
EPA 6010B
Certificate # L2284
Analyte
Th-234
Tl-208
U-235
V-48
Y-88
Zn-65
Zr-95
Aluminum
Antimony
Arsenic
Barium
Beryllium
Boron
Cadmium
Calcium
Chromium
Cobalt
Copper
Iron
Lead
Magnesium
Manganese
Molybdenum
Nickel
Potassium
Selenium
Silica
Silver
Sodium
Strontium
Thallium
Tin
Titanium
Vanadium
Page 8 of 15
LABORATORY
ACCREDITATION
BUREAU
Non-Potable Water
Technology
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
CVAA
Preparation
SPLP
TCLP
Metals Prep
Solid and Chemical Materials
Technology
Gas Proportional Counting
Gas Proportional Counting
Gas Proportional Counting
Gas Proportional Counting
Gas Proportional Counting
Liquid Scintillation Counting
Liquid Scintillation Counting
Liquid Scintillation Countin~
Gas Proportional Counting
Gas Proportional Counting
Fonn 403.8 -Rev I -4-11-11
Certificate # L2284
Method Analyte
EPA 6010B Zinc
EPA 200.7 Aluminum
EPA 200.7 Antimony
EPA 200.7 Arsenic
EPA 200.7 Barium
EPA 200.7 Beryllium
EPA 200.7 Boron
EPA 200.7 Cadmium
EPA 200.7 Calcium
EPA 200.7 Chromium
EPA 200.7 Cobalt
EPA 200.7 Copper
EPA 200.7 Iron
EPA 200.7 Lead
EPA 200.7 Magnesium
EPA 200.7 Manganese
EPA 200.7 Molybdenum
EPA 200.7 Nickel
EPA 200.7 Potassium
EPA 200.7 Selenium
EPA 200.7 Silica
EPA 200.7 Silver
EPA 200.7 Sodium
EPA 200.7 Strontium
EPA 200.7 Thallium
EPA 200.7 Tin
EPA 200.7 Titanium
EPA 200.7 Vanadium
EPA 200.7 Zinc
EPA 7470A Mercury
Method Type
EPA 1312 Buffered Aqueous Extraction
EPA 1311 Buffered Aqueous Extraction
EPA 3010A Acid digestion
Method Analyte I
EPA 900 Modified / 9310 Modified Gross Alpha
EP A 900 Modified / 9310 Modified Gross Beta
EP A 904 Modified / 9320 Modified Radium 228
EPA 905 Modified Strontium 89/90
EPA 905 Modified Strontium 90
EPA 906.0 Modified Tritium
EPA C-O I Modified Carbon 14
DOE HASL 300 TC-Ol Technetium 99
SM 7500 Ra B Modified Radium 226
SM 7500 Ra B Modified Total Radium
Page 9 of 15
LABORATORY
ACCREDITATION
BUREAU
Solid and Chemical Materials
TechnoloeY
Alpha-Spec
Alpha-Spec
Alpha-Spec
Alpha-Spec
Alpha-Spec
Alpha-Spec
Alpha-Spec
Alpha-S_pec
AlEha-S~ec
Alpha-Spec
Alpha-Spec
Alpha-Spec
Alpha-Spec
Alpha-Spec
Alpha-Spec
Alpha-Spec
Alpha-Spec
Alpha-Spec
Alpha-Spec
Alpha-Spec
Alpha-Spec
KPA
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Fonn 403.8 -Rev I -4-11-11
Method
EPA 907 Modified
EPA 907 Modified
EPA 907 Modified
EPA 907 Modified
EPA 907 Modified
EPA 907 Modified
EPA 907 Modified
DOE HASL Po-2 RC
EP A 907 Modified
EPA 907 Modified
EP A 907 Modified
SM 7500 Ra Modified
LANL ER 200 Modified
LANL ER 200 Modified
LANL ER 200 Modified
LANL ER 200 Modified
ASTM D3972 Modified
ASTM D3972 Modified
ASTM 03972 Modified
ASTM D3972 Modified
ASTM D3972 Modified
ASTM D5174 Modified
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
Certificate # L2284
Analvte
Am-24 1
Am-242/243
Cm-242
Cm-243/244
Cm-244
Cm-245/246
Np-237
Po-21 0
Pu-238
Pu-239
Pu-239/240
Ra-226
Th-227
Th-228
Th-230
Th-232
U-233/234
U-234
U-235
U-235/236
U-238
Uranium, Total
Ac-227
Ac-228
Ag-I08m
Ag-llOm
Al-26
Am-24 1
Am-243
As-72
As-73
As-74
Ba-133
Ba-140
Be-7
Page 100fl5
LABORATORY
ACCREDITATION
BUREAU
Solid and Chemical Materials
Technology
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma S~ec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Sp_ec
Gamma Spec
Gamma Sp_ec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Fonn 403.8 -Rev 1-4-11-11
I
Method
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-O l-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-O l-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-O l-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5 .2.3
HASL 300 Ga-O l-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-O l-R
DOE 4.5.2.3
HASL 300 Ga-O l-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
Certificate # L2284
Analyte
Bi-211
Bi-212
Bi-214
Br-76
Br-77
Br-82
Cd-109
Ce-139
Ce-14l
Ce-144
Cf-249
Cf-25 1
Cl-39
Cm-243
Co-56
Co-57
Co-58
Co-60
Cr-51
Cs-134
Cs-135
Cs-136
Cs-137
Eu-152
Page 11 of 15
LABORATORY
ACCREDITATION
BUREAU
Solid and Chemical Materials
Technology
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Form 403.8 -Rev I -4-11-11
Method
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-O I-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5 .2.3
HASL 300 Ga-O l-R
DOE 4.5.2.3
Certificate # L2284
Analyte
Eu-154
Eu-155
Fe-59
Gd-153
Ge-68
Hf-181
Hg-197m
Hg-203
1-131
Ir-I92
K-40
Kr-85
La-140
Mn-54
Na-22
Na-24
Nb-94
Nb-95
Nd-147
Np-236
Np-237
Np-239
Os-191
Pa-23 1
Page 12 of 15
LABORATORY
ACCREDITATION
BUREAU
Solid and Chemical Materials
Technolo2Y
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Form 403.8 -Rev 1 -4-1\-\\
Method
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol -R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
Certificate # L2284
Analvte
Pa-234m
Pb-210
Pb-211
Pb-212
Pb-214
Pm-144
Pm-146
Po-209
Ra-223
Ra-224
Ra-226
Ra-228
Rb-83
Rb-86
Rh-101
Rh-I06
Rn-222
Ru-l03
Ru-106
Sb-124
Sb-125
Sc-46
Se-75
Sn-1l3
Page 13 of 15
LABORATORY
ACCREDITATION
BUREAU
Solid and Chemical Materials
Technolo2Y
Gamma S12ec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
Form 403.8 -Rev I -4-11-11
Method
HASL 300 Ga-Ol-R
00E4.5.2.3
HASL 300 Ga-Ol-R
00E4.5.2.3
HASL 300 Ga-Ol-R
00E4.5.2.3
HASL 300 Ga-Ol-R
OOE 4.5.2.3
HASL 300 Ga-Ol-R
OOE 4.5.2.3
HASL 300 Ga-Ol-R
00E4.5.2 .3
HASL 300 Ga-Ol-R
00E4.5.2.3
HASL 300 Ga-Ol-R
OOE 4.5.2.3
HASL 300 Ga-Ol-R
00E4.5.2.3
HASL 300 Ga-Ol-R
OOE 4.5.2.3
HASL 300 Ga-Ol-R
00E4.5.2.3
HASL 300 Ga-Ol-R
00E4.5.2.3
HASL 300 Ga-O l-R
00E4.5.2.3
HASL 300 Ga-Ol-R
00E4.5.2.3
HASL 300 Ga-O 1-R
OOE 4.5.2.3
HASL 300 Ga-Ol-R
00E4.5.2.3
EPA6010B
EPA 6010B
EPA 6010B
EPA 6010B
EPA 6010B
EPA 6010B
EPA 6010B
EPA 6010B
EPA 6010B
EPA 6010B
EPA 6010B
EPA 6010B
EPA 6010B
EPA 6010B
EPA 6010B
EPA 6010B
EPA 6010B
Certificate # L2284
Analyte
Sn-126
Sr-85
Ta-182
Tb-160
Th-227
Th-228
Th-230
Th-231
Th-232
Th-234
TI-208
U-235
V-48
Y-88
Zn-65
Zr-95
Aluminum
Antimony
Arsenic
Barium
B~llium
Boron
Cadmium
Calcium
Chromium
Cobalt
Copper
Iron
Lead
Magnesium
Manganese
Molybdenum
Nickel
Page 14 of 15
LABORATORY
ACCREDITATION
BUREAU
Solid and Chemical Materials
Technology
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
ICP
CVAA
Preparation
SPLP
TCLP
Metals Prep
Method
EPA 6010B
EPA 6010B
EPA 6010B
EPA 6010B
EPA 6010B
EPA 6010B
EPA 6010B
EPA 6010B
EPA 6010B
EPA 6010B
EPA 7471A
Method
EPA 1312
EPA 1311
3050B
1) This laboratory offers commercial testing service.
~D$2? Approved by: _"';"~ __ ' __ -----___ ...;;:::::!I""'-=--__
R. Douglas Leonard'""
Chief Technical Officer
Issued: 3/24111 Revised: 8/2/12 Revised: 2/5/13
Fonn 403.8 -Rev 1-4-11-11
Certificate # L2284
Analvte
Potassium
Selenium
Silica
Silver
Sodium
Strontium
Tin
Titanium
Vanadium
Zinc
Mercury
Tvpe
Buffered Aqueous Extraction
Buffered Aqueous Extraction
Acid digestion
Date: February 5, 2013
Page 15 of 15
I ~
LABORATORY
ACCREDITATION
BUREAU Certificate # L2284
Scope of Accl~editation
For
Outreach Technologies, Inc.
d.h.a._ Outtea~cJLLaboratory
3 i 1 N Aspen Avenue
Broken Arrow, OK 74012
Donna Eidson
918-251-2515
In recognition of a successful assessment to ISOIIEC 17025:2005 and the requirements of the DoD
Environmental Laboratory Accreditation Program (DoD ELAP) as detailed in _the DoD Quality Systems
Manual for Environmental Laboratories (DoD QSM v4.2) based on the National Environmental
Laboratory Accre4.it~~tQ~ QQnf~_~~nce Chapter 5 QUC1litx~~ystems Standard (NELAC~yg!ed Revision
June 5, 2003), accreditattoncis gn,mted-to-Outreac~:-Laboratory to perform the follo~g. tests:
.: .... -~.. ... • ,'''.. to :::-_._':_"'" --... -".
Accreditation granted-through~ March 24,2014
Testing -Environmental
Non-Potable Water .. . . .
Technology Metiu)d Analyte--.. -...
GaS Pioporlio~al Counting EPA 900 / 9310 Gross 'Alpli~--. -: -
Gas Proportional Counting EPA 900 19310 Gross Beta
Gas Proportional Counting EPA 904/9320 Radium-z~8·--·
Gas Proportional Counting EPA 90S 8trontiupJ 89/90
Gas Proportional Counting EPA 90S StrontitmJ 9.0
Liquid Scintillation Counting EPA 906 Tritium
Liquid Scintillation Counting EPAC-Ol Carbon-l 4
Liquid ScintUIation Counting DOE HA8L TC-01 Technetium 99
Gas Proportional Counting SM 7S00-RaB Radium 226
Gas Proportional Counting SM7S00-RaB Total Radium
Liquid 8cLfltillation Counting 8M7S00-RnB Radon 222
Alpha-Spec •.. EPA 907-Moaified Am-241
Alpha-Spec EPA 907 Modified Am-242/243
Alpha-Spec EPA 901 Modified Cm-242
Alpha-Spec EPA 907 Modified Cm-243/244
Alpha-Spec EPA 907 Modified Cm-244-
Alpha-Spec EPA 907 Modified Cm-24S/246
Alpha-Spec EPA 907 Modified Np-237
Alpha-Spec DOE HASL 300 Po-2 RC Po-210
Alpha-Spec -EPA 901 Modified Pu-238
Alpha-Spec EPA 907 Modified Pu-239
Alpha-Spec EPA 907 Modified Pu-239/240
Alpha-Spec 8M 7S00Ra B Modified Ra-226
Alpha.--Spec LANL ER 200 Modified Th-227
Alpha-Spec LANL ER 200 Modified Th-228
Form 403.8-Rev 1-4-11-11 Page I of15
J
.. J
I
I
LABORATORY
ACCREDITATION
BUREAU
No-n~Poiable Water
Technology
Alpha-Spec
Alpha-Spec
Alpha-Spec
Alpl1a·:Spec
Alpl;a~Spec -
Alpha-Spec
Alpha-Spec
KPA
Gahuna Spec
Gamma Spec
-
.... _ .. . .
,Gamma-Spec
--... -_. ,-
Gamma Spec
GrunmaSpec
GarnmaSpec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Fonn 403.8-Rev 1-4-11-11
... .
-
.. . .
Method
LAhlL ER 200 Modified
LANL ER ~.OO·Modified
ASTM't>3972
ASTIVfD3972
AS1M"D3972
ASTMD3972
ASTMD3972
ASTMD5174
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
'EPA901.1
HASL3~OO ;Ga:-.O l-R
])OE'4--5-2-J ---": ;-.. -...
EPA201.1
HASL=-300--Ga-O 1-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE4.S.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-OI-R
DOE 4.5.2.3
Certificate # L2284
.. -' . -._ ..... , ... . .
Analyte
Th-23 0
Th-232
U-233/234
U-234
T U-235
U-23 5/230
U-238
Uranium, Total
-Ac-227
Ac-228
-'-" --.-.,-~ .. ~-
Ag:o-108ifr~:·;.
.. .: .. _ .....
A,g-llOm
AI-26 . -
--.~ -
--.
Am-241 .
Ani-243
As-72
As-73
As-74
Ba-I33
Ba-140
Be-7
Page2of15
~)
LABORATORY
ACCREDITATION
BUREAU
Non-Potable-Water'
Technology
Gamma Spec
-.
Gamma Spec
GammaSp.ec
Gamma Spec
Gamma Spec .. . .
-. ----. ~-. ..
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Sl2.ec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Fonn 403.8 -Rev 1 -4-11-11
. .. , --
Method
EPA 901.1
HASL 300 Ga-O l-R
DOELJ.~S:23
. EPA901. 1
HASr:300:·:Ga~ l:.;R -
OOE-4:S;2.S
EPA 901.1
HASL 300 Ga-01-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE4~S.2.3
EPA 901.1
HASL JOO Ga"Ol-R
DOEA.S.2.3
·EPA901.1
HA$.~~3QO -Gi·QI-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-O loR
DOE 4.5.2.3
EPA 901.1
HASLJOO Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE4.S.2.3
EPA 901.1
HASL 300 Ga-01-R
DOE4.S.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
Certificate # L2284
.. ~ _ . -
Analyte
Bi-211
-.... j -----......
Bi".212
Bi-214
Br-76
.-
Br.~l1
~
'-:-:'; ... ,
~ .
-•• -j
Br-82 -
Cd-I09
C~J3.9 ...
,., .. .
Ce-141
Ce-144
Cf-249
Cf-251
Cl-39
C1l1-243
Co-56
Co-57
Page 3 ofl5
.J
LABORATORY
ACCREDITATION
BUREAU
NOB"'Potable"Water ~ .
TechnoloJlY
-
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
... -.~ . -----. ----.------:>._---~ ..-
Gamma Spec -
GammaSIlec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Form 403.8 -Rev 1 -4-11-11
-.. ~ --,.
Method -
EPA90Ll
HASL 300 Ga;.Ol-R
DOE 4:52.3
·-EPA 9U1.1
HASL 300 "Ga':OI-R
BOE-45;2-3
EPA 90l.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-:01-R
DOE 4.5.2.3
. EPA:90 1:1
HASb3lro13a:OI -R
00E4.5:2.3
EPA-90Ll
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
. DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
ElV1L 4.5.2.3
EPA 901.1
HASL 300 Ga-OI-R
DOE 4.5.2.3
EPA90Ll
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
Certificate # L2284
. -------. ~, .
AnaJyte
Co-58
Co-60
Cr-Sl
Cs-134
Cs-13.5
_a •
~ . _ ..
Cs-136'"::-'-.. -
Cs-137
_.
Eu-152 --.,. --
Eu-154-' -
0.' ...
Eu-ISS
Fe-59
Gd-1S3
Ge-68
Hf-181
HK"197m
Hg-203
Page 4 of 15
I
lABORATORY
ACCREDITATION
BUREAU
. Non-p'otable Wafer
Technology
Gamma Spec
Gamma Spec
Gamma~pec
Gamma Spec
GammaSp~
.' .
, ..... .. . .. ..
Gamma Spec --'" ----"
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
FOml403.S-Rev 1-4-11-11
. .
Method
EPA 901.1
HASL 300 Ga~O l-R
DOE 4.5.2.3
EPA90L1
HASL-300.Ga"Ol-R
DOE 4.5.2.3-R
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-O 1-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
_POE 4.5.2 .. :3
EPA90Ll
HASL"30CfG a:0 1-R ------~ DOE 4.5.2.3
l!PA9or.r ·
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-01-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga~Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE4.S.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-01-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3
Certificate # L2284
. --.-
Analyte
1-131
Tr-192
K-40
Kr-85
La-l4.~t ..
_.:----=
"-Mn-54'--.
. _ _ ... _ .. r -..
..
Na-22
-..
Na-24 _ ' ... -.. -'
-_ ..
.
Nb-94 " " .
--.-.
Nb-95
Nd-147
N..Q-236
Np-237
~-239
Os-191
Pa-231
Page 5 ofl5
) -
-.
. J
-)
LABORATORY
ACCREDITATION
BUREAU
Non~Potable W~ter-··
Technology
Gamma Spec
I' .. .
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
. . " _. .
. damma 'Spec .. -.
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
GammaS ec
Gamma Spec
Gamma Spec
Gamma Spec
Form 403.8-Rev 1-4-11-11
. .
..
Certificate # L2284
. . . .. . . . . ..
Method Analyte
EPA 901.1
T-T SL.3.Ot)..Qa..O 1 _R
DOE 4.5.2.3 Pa-234m
. ERA90Ll
HA~J;:~QQ:~c.O l-R . .
DOE 4.5.Z.3 Pb-2IO
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3 Pb-2II
EPA 901.1
HASL300 Ga-OI-R
DOE4.S.2.3 Pb-212
EPA 901.1
HAS~'3dO Ga-Ol-R
.
.. .
DOE 4.5.2.3 Pb-214
EPA 901.1 " .. _. -HA:S:C:30(j'~Ga~Ol-R .. -=.:.:..-D6E4.5.2~3 Pm-144--'-;-c
"WA"9m.J ___ r
HASL 300 Ga-Ol-R
DOE4.S.2.3 Pm-146
EPA 901.1
HASL 300 Ga-Ol-R .... -
DOE 4.5.2.3 Po-209 .-
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3 Ra-223
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3 Ra-224
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3 Ra-226
EPA 901.1
P..ASL 300 Ga-Ol-R
DOE 4.5.2.3 Ra-228
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3 Rb-83
EPA 901.1
HASL 300 Ga-Ol-R
DOE4.S.2.3 Rb-86
EPA 901.1
HASL 300 Ga-Ol-R
DOE4.S.2.3 Rh-IOI
EPA 901.1
HASL 300 Ga-Ol-R
DOE 4.5.2.3 Rh-106
Page 6 of1S
LABORATORY
ACCREDITATION
BUREAU
-N'on;!1fufiib1e-'Wbte~' --
Technology
Gamma Spec
-. . -00--'--_., .--.. . , ... -. --" ~ -:. -
Method
EPA 901.1
HASL3"OO-'Ga=O 1-R
PQE-4.s~2:3
-~p A-90:1-; 1
Certificate # L2284
--, .,' --~ . ---,---.;........", . .:-._-., ---
Analyte
Ru-l03
-. .. ~ .... . -HASIr-300 Oa-Ol-R -_ . . .. _ ... -.. -.. ---...... .. -
, , __ , .•. ,.9~p?·~ §P~I?_, .... , ..•.
.. .. .. ... -------...... ---_ ... _--..... Ru:106 DOE4.S.2.3 ........ -----.---EPA 901.1
HASL 300 Ga-Ol-R
Gamma Spec DOE4.S.2.3 Sb-124
EPA 901.1
HASL 300 Ga-01-R
Gamma Spec DOE 4.5.2.3 Sb-12S
EPA 901.1
HASL 300'Ga-01-R ..
Gamma Spec DOE 4.5.2.3 Sc-46 . ~ " -EPk90I:1 . , -HASL' -36.0 'Ga-:O l-R .... -"', _.-...... __ ... ....-. .. .. --'DOE '4~~2'] -"Ganniui Spec Se-75~---C
. -----.... :'Er.k9"Q171 ' .
HASL 300 Ga-Ol-R
Gamma Spec DOE4.S.2.3 Sn-l13
EPA 901.1
HASL JOO Ga-Ol-R .....
Gamma Spec DOE 4.5.2.3 Sn-126 --
EPA 901.1 -. ..
HASL 300 Ga-Ol-R -Gamma Spec DOE4.S.2.3 Sr-8S ' ..
EPA 901.1
HASL 300 Ga-Ol-R . -..
Gamma Spec DOE 4.5.2.3 Ta-182
EPA 901.1
HASL 300 Ga-Ol-R
Gamma Spec DOE4.S.2.3 Tb-160
EPA 901.1
HASL 300 Ga-Ol-R
Gamma Spec DOE4.S;2.3 Th-227
EPA 901.1
HASL 300 Ga-Ol-R
Gamma Spec DOE 4.5.2.3 Th-228
_____ EPA9.01.L _ .. -_. ----
HASL 300 Ga-Ol-R
Gamma Spec DOE4.S.2.3 Th-23 0
EPA 901.1
HASL 300 Ga-Ol-R
Gamma Spec DOE4.S.2.3 Th-231
EPA 901.1
HASL 300 Ga-Ol-R
Gamma Spec DOE 4.5.2.3 Th-232
Fom1403.8-Rev 1-4·11-11 Page? oflS
'"J . ..
LABORATORY
ACCREDITATION
BUREAU
. Noil':'Pot'rible 'W:ateT-~" --.
Technology
Gamma Spec
.. .... -..... -... ---
Gamma §p.ec ..
Gamma Spec
Gamma Spec
Gamma Spec .
. -, --.--.
Gainfua Spec .. I
Gamma Spec
Iep
ICP rcp
ICP
rcp
rcp
ICP
rcp
rep
rcp
ICP-
rcp
rcp
TCP
rcp
rcp
rcp
ICP
rcp
rep
ICP
Tep
ICP
rcp
ICP
ICP
ICP
Fonn 403.8 -Rev 1 -4-11-11
. . " . ..... .
r'_ •• ~ ... _ -". -'---__ I
.-... ---., -
Method
EPA 9.01.1
HASL30.o-Oa,:,.oI-R
nOE:4,5.2.3
~P.lk20l;1 -. --,--HAS:b-300 Ga-Ol-R .. .. ...
bOE __ 4~5.2.3 ' --... ,. ,.-~ .... -o. __ .,.
EPA 9.01.1
HASL 3.0.0 Ga-Ol-R
DOE 4.5.2.3
EPA 9.01.1
HASL 3.0.0 Ga-.oI-R
DOE 4.5.2.3
EPA 9.01.1
HASL 30.o'Ga-Ol-R
DOE 4.5.2.3
EPA9.oLI
HASL: 30.0' 6a"-.o l.;R
DOE 4.5.2.3
··:E~*,2_9~-·'1
HASL 30.0 Ga-.oI-R
DOE 4,5.2.3
EPA6.oI.oB
EPA 6.oI.oB
EPA 6.oI.oB
EPA601.oB
EPA601.oB
EPA601.oB
EPA 60 JOB
EPA60l.oB
EPA6010B
EPA601.oB
EPA 60 lOB
EPA6010B
EPA601.oB
EPA 6.oI.oB
EPA 6.oI.oB
EPA6.oI.oB
EPA 6.oJOB
EPA 6.oI.oB
EPA 60 JOB
EPA 6.oIOB
EPA 6.0 lOB
EPA.6010B
EPA6010B
EPA60l.oB
EPA601.oB
EPA 60 JOB
EPA 60 lOB
Certificate # L2284
, . --.. , .. -... -... _.. .. .. --..
~alyte
Th-234
-. -.. --"
TI-2.o8
U-235
V-48
Y-88
...... _u ,
. ...
Zn-65-:C:--~-'
.
Zr-95
Aluminum
Antimo~ .-..
Arsenic._
Barium'--
B~llium
Boron . ..
Cadmium
Calcium
Chromium
Cobalt
Copper
Iron
Lead
Magnesium
Manganese
Mo!x,bdenum
Nickel
-Potassium
Selenium
Silica
Silver
Sodium
Strontium
Thallium
Tin
Titanium
Vanadium
Page 8 of IS
. J
LABORATORY
ACCREDITATION
BUREAU
Non.'Potable =Water
Technology
ICP
ICP
ICP
ICP
rcp
rcp
rcp
ICP
ICP
rcp
rcp
rcp
rcp
ICP
ICP .
rc~
--':--I€P-"--
rcp -_.
ICP
Iep
rep
rep
ICP
ICP
rcp
ICP
ICP
ICP
rcp
CVAA
Preparation
SPLP
TCLP
Metals Prep
SOlid and.Chemical Materials.
Technology
Gas Proportional Counting
Gas Proportional Counting
Gas Proportional Counting
Gas Proportional Counting
Gas Proportional Counting
Liquid Scintillation Counting
Liquid Scintillation Counting
qquid Scintillation Counting
Gas Proportional CountinR
Gas Proportional Countir'"1g
Form 403.8 -Rev 1 -4·11·11
Certificate # L2284
.. . -.... ", J I . -. . . .. . . ... ,. -.. ' .. .. .
Method Analyte
EPA 60 lOB Zinc
EPA: 200':7 Aluminum
EPA 200.7 Antimony
.EPk4.00.7 Arsenic
. -EPA ·200; 7 Barium
EPA 200.7 Beryllium
EPA 200.7 Boron
EPA 200.7 Cadmium
EPA 200.7 Calcium
EPA 200.7 Chromium
EPA 200.7 Cobalt
EPA 200.7 C~pper
EPA 200.7 Iron
EPA 200.7 Lead
. EPA-200.1 Magnesium
EPA 200.7 Manganese .
~ EPA:200a . . Moli:bde1i~~' . ..
EPA-200.? Nickel: .. o 5 ..
EPA-200;7 Potassium
EPA 200.7 Selenium .
EPA 200.7 Silica
EPA 200.7 Silver
EPA 200.7 Sodium ' . .,.
EPA 200.7 Strontium . .-.
EPA 200.7 Thallium' .
EPA 200.7 Tin...... .. _. _.
EPA 200.7 Titanium
EPA 200.7 Vanadium
EPA 200.7 Zinc
EPA 7470A Mercury
. Method Type
EPA l312 Buffered Aqueous Extraction
EPA l311 Buffered Aqueous Extraction
EPA3010A Acid digestion
Method An~e
EPA 900 Modified 19310 Modified . -.Gross Alpha
EPA 900 Modified / 9310 Modified Gross Beta
EPA 904 Modified / 9320 Modified Radium 228
EPA 905 Modified Strontium 89/90
EPA 905 Modified Strontium 90
EPA 906.0 Modified Tritium
EPA C-O 1 Modified Carbon 14 .
DOE HASL 300 TC-Ol Technetium 99
SM 7500 Ra B Modified Radium 226
SM 7500 Ra B Modified Total Radium
Page 9 ofIS
LABORATORY
ACCREDITATION
BUREAU
. Solid"and:ClienuCitI.'M8teJ'ials.
Technol~
Alpha-S~ec
Alpha-Spec
Alpha-Spec
Alpha:-Spec
-_.. ... '. AIEha-Spec.
Alpha-Spec
Aipha-Spec
Alpha-Spec
Alpha-Spec
Alpha-Spec
Alpha-Spec
Alpha-Spec
Alpha-Spec
Alpha-S..pec
Alpba:§pe9..
Alpha-Spec ' .
-. -" Alplia-Sj"ec.;,:,:-=--: .~-.. -
Alpha-Spec
Alpha~Spec
Alpha-Spec
Alpha-Spec
KPA
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma~pec
GamrnaSpec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Form 403.8-Rev 1-4·11-11
'-0'
" " oJ -:. ;-
• c -" -. ~ .. . -
Method
EPA 907 Modified
EPA 907 Mb'dified
EPA 907 Modified
EPA 9.0.'LMoJlified
EP-Au907 .Modified .. -
EPA 9Q7 Modified
EPA 907 Modified
DOE HASL Po-2 RC
EPA 907 Modified
EPA 907 Modified
EPA 907 Modified
SM 7500 Ra Modified
LANL ER 200 Modified
LANL ER 200 Modified
LANL :P:R2QO Modified
LANLER200:Modified
ASJ:MD39-72""MOdified
ASTM D3.272 Modified
ASTM D39v;2· MQdIfied
AS1M D3972 Modified
ASTM D3972 Modified
ASTMD5174 Modified
HASL 300 Ga-Ol-R
DOE 4.52.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HA~k ~QO Ga:-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-O l-R
DOE 4.5.2.3
HASL 300 Ga-O l-R
DOE4.S.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
Certificate # L2284
" •• _ 9_ • "' ;---.. .. -.
Analyte
Am-24 1
Am-242/243
Cm-242
Cm-243/244 .'-----
---Cm-244
Cm-245/246 ._--Np-237
Po-2l0
Pll-238
Pll-239
Pll-239/240
Ra-226
Th-227
Th-228
l'h~230
'Eli~232
... ' -U-133f2?4
U'::Z34'
U-235·
U-235/136
U-238-
Uranium, Total ---
Ac-22-7-... -.
Ac-228 .
Ag-I08m
...... --.. --
Ag,:"UOm
AI-26
Am~241
Am-243
As-72
As-73
As-74
Ba-133
Ba-140
Be-7
Page IOofl5
.)
)
LABORATORY
ACCREDITATION
BUREAU
~ S<rtid 8Qd 'Cb@liealMaterials
TechnoloRY
Gamma Spec
Gamma Spec
Gamma Seec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma-Spec
.. ,
Gamma Spec'
--
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma~pec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Form 403.8-Rev 1-4-11-11
-.~ --0 -___ ,.~
Method
HASL 300 Ga-Ol-R
DOE·-4·.5 .~:3
HASL 300 Ga-Ol-R
DOE.4.5.2.3
HASL ·3QD.G;j.-:Ot-R
. DOE 4:5:2:3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE4.S.2.3
HASL 300 Ga.-O l-R
DOE 45:2:3
HAS1.-300 Ga-'Ol-R D0ir-4ciS·;2.3
HAShc300-Ga-0l-R
nOE4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
-DOE 4.5.2.3
HASL300 Ga':Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE4.S.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
Certificate # L2284
:--..
Anal;rtc
Bi-211
Bi-212
. -. 8i-214"
Br-76
Br-77
... Br-82
Cd-l09
Ce=:139
Ce~t41
Ce-l44
Cf-249
-Cf-251
Cf-39
Cm.;243
I ,
Co-56
Co-57
Co-58
Co-60
Cr-51
Cs-134
Cs-135
Cs-136
Cs-137
Eu-152
Page 11 of15
)
LABORATORY
ACCREDITATION
BUREAU
Solid :anU:CIie1ffial:Matef.oo' ..
Tecbnolo2Y
Gamma Spec
Ganuna Spec
-
Gamma Spec
GammaS.I!.ec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec. -.
Ganima Spe'c --._---_ . .,. ..
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma~~ec
Gamma Spec
OammaSpec
Gamma Spec
OammaSpec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Fonn 403.8-Rev 1-4-11-11
-
.
--.... .. :
Method
HASL 300 Ga-Ol-R
DOE4.S.2:3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL.3.00 ... Ga-.Q1-R
DOE4.S.2.3
HASL 300 Ga-O l-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE4.S.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.52.3
HASL 300 Ga-O l-R
DOE 4.5.2:3
IJAS~:?1>Q:.G.:a-p l -R
bOE -4.5:;L3
HASIi~90:6a~Ol-R
DOE 4.52.3
HASL300 Ga-Ol-R
00E4.5.2.3
HASL 3QO Ga-O l-R
DOE 4.5.2.3
HASL 300 Ga-Ol -R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Oa-O l-R
DOE 4.5.2.3
HASL 300 Oa-O l -R
DOE 4.5.2.3-
HASL300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-O l-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE4.S.2.3
Certificate # L2284
. " . .. , ..
Analyte
Eu-154
Eu-I55
..
Fe-59
Gd-153
Ge-68
Hf-181
. Hg-197m ..
Hg~03
• .=.:.~
I-f3-i ..
Ir-I'92
K-40
-
Kr-85
,.
La-140
Mn'754
.
Na-22
Na-24
Nb-94
Nb-95
Nd-147
Np-236
Np-237
Np-239
Os-191
J
Pa-231
Page 12ofl5
)
LABORATORY
ACCREDITATION
BUREAU
-S.olld:.a\ia_CJi.~IIiii!al Matel~als.:.
Tecbnoiou
Gamma Spec
Gamma Spec
Gamma Spe"c .
Gamma Spec
Gamma Spec
Gamma Spec
GammaS~c
GammaSp-ec
--. " . ..
GammaSpec" .
. -"
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Form 403.8-Rev 1-4-11-11
-"
-
, . . --. -"
Method
HASL 300 Ga-Ol-R
DQE4.S .. Z.3
HASL JOO'Ga';Ol-R
pOEA.S.2.3
HASr; .. 3Jj:O~Ga~Dl~R
DOE-4.5:23
HASL 300 Ga-O l -R
DOE 4.5.2.3
HASL 300 Ga-Ol~R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
D0E-45.2;3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
00£45.23
~~:~.:9QQa~QI-R
D0E4:5.23
HASI:. ~·OO·Ga~O l-R
DOE 4:5:2:3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Qa-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
00E4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-01-R
00E4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
00E4:5.2.3
HASL 300 Ga-Ol-R
00E4.5.2.3
HASL 300 Ga-Ol-R
00E4.5.2.3
HASL 300 Ga-Ol-R
00E4.5.2.3
HASL 300 Ga-Ol-R
--DOE 4.~·.2.3 .
HASL 300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE 4.5.2.3
Certificate # L2284
. .
Analyte
Pa~234m
Pb-21O . .
. " Pb.:211
Pb-212
Pb-214
Pm-l44
:'Pm-146 ..
1~o-:209
~~.=:.---; ......
Rii223.
.. ---
Ra-ii4'
Ra-2~6' .
.. -.
Ra-228
~-. .
Rb,.83 .. . ..
Rb-86
----..
Rh-101
Rh~106
Rn-222
Ru-103
Ru-106
Sb-124
Sb-125
.. . Sc.:46
Se-75
Sn-l13
Page 13 ofl5
LABORATORY
ACCREDITATION
BUREAU
_ Sl)lid Sincl" ChemicaJ Materials
Technology
Gamma Spec
Gamma Spec
.
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec
Gamma-S:eec'
., -Gamm~lSpec .
--
Gamma Spec
Gamma Spec
Gamma Spec .-
Gamma Spec
Gamma Spec
Gamma Spec
Gamma Spec . rcp
rcp
rcp
ICP
ICP
rcp
rcp
ICP
ICP
rcp
ICP
ICP
ICP
ICP
ICP
ICP
ICP
Form 403.8-Rev 1-4-11-11
..
.. -
-. " -,.. -----' _. "-"-.. _ .. '*. - ....... -.
Method
HASL 300 Ga-Ol-R
DOE 4.5:23
HASL 300-Ga~01 -R
rrOEA.S.tJ
HASLJ1)D :Ga:-OJ-R .
DOE4.5~23
HASL 300 Ga~Ol-R
DOE4.S.2.3
HASL 300 Ga-Ol-R
DOE4.S.2.3
HASL 300 Ga-Ol -R
DOE4.S.2.3
HASL 300 Ga-Ol-R
DOE4.S.2.3
HASL 300-Ga-Ol-R
DOE '4.52.3
HASb:g OO:Ga'-O I-R
DdE4.5;2~3
HASl?:300:Qli=OI-R
DOE·4.5.2.3
HASL 300 Ga-Ol-R
DOE4.S.2.3
HASL 300 Oa-Ol-R
DOE 4.5.2.3
HASL 300 Ga-OI -R
DOE 4.5.2.3
HASL 300 Ga-O I-R
DOE 4.5.2.3
HASL300 Ga-Ol-R
DOE 4.5.2.3
HASL 300 Ga-Ol-R
DOE4.S.2.3
EPA 6010B
EPA6010B
EPA 6010B
-EPA-6010B
EPA6-010B
EPA 60 lOB
EPA 6010B
EPA6010B
EPA 6010B
EPA6010B
EPA 60 lOB
EPA 6010n '-
EPA 60 lOB
EPA6010B
EPA6010B
EPA6010B
EPA 6010B
Certificate # L2284
. -.. , -.-. , -."-.. ' .
Analyte
Sn-126
Sr-85
Ta-182
Tb-160
Th-227
Th-228
Th-23 0
TJi-':231
.-~~~ Th~2~2
-
Th-234
TI-208'
----U-235 _ .. .
V-48
.---'-.. -_. ~
V-SS-
.. ", __ ,_ ..
Zn-65
Zr-95
Aluminum
Antimony
Arsenic
Barium
Beryllium
Boron
Cadmium
Calcium
Chromium
Cobalt
Copper
lron
Lead
Magnesium
Manganese
Molybdenum
Nickel
Page 140f15
LABORATORY
ACCREDITATION
BUREAU
.. -... --; , ';Solid-apU e:rreIDicat~teri~'''' . . , '.
Technology Method
ICP EPA6010B
ICP E~A.!5910.13_ rcp EPA 6010B
ICP EP.A. .. 60iOB·
ICP EEA.6UU)B.
ICP E~A'-~OtO;a
Iep EPA 6010B
Iep EPA6010B
ICP EPA 60 lOB
ICP EPA6010B
ICP EPA6010B
CVAA . --EPA 7471 A
Preparation Method
SPLP EPA. 1312
TCLP EPA 1311
Metals 'Prep .3050B. -_ ... _ .. _---. -:-~-~,.--. ; .. :---. .... ,.-.. ~. . .......... ~ . ---.-..... -
1) This labOratory' offers coriunercial testing serVi~¢':'--':-----,'
: .-:. -" -, . '.--
~? Approved by: _~~_' _____ -""""-"_~_.::::!!110,",-,:,..--_
R. Douglas Leonarr
Chief Technical Officer
Issued: 3/24111 Revised: 8/2/12
Certificate # L2284
· . . . ' ~ . . .. -----. . --" , ..
Analyte
Potassium
Selenium
Silica
Silver
Sodium
Strontium
TIlalliulU
Tin
· Titanium
Vanadium
Zinc
c • Mercury
Type
Buffered::A~ueous Extraction
Buffered Aq~~ous Extraction
Acid::tljg~stion · , , _.-
Date: August 2.2012
Form 403.8-Rev 1 ~4·11-11 Page 150fl5
ATTACHMENT 3
EFRI (formerly Denison)/UDEQ Protocol for Determining Whether Alternate Feed
Materials Are RCRA Listed Hazardous Waste
01 • , ••• " •••
Mic.h~cI 0, l.~avill
Gcvcmor
Diann\! El r.;id~on, l'I1.{},
r:!\:('i:U{.v(. Dn~c.LOr
Dennis R. DClwn~
State of Uta11
DEPARTMENT OF FSVrRONYlli:---;TAL QUALiTY
DIVISION Of SOLID AJ:-,;D HAZARDOI.;S WASTE
2118 North 1460 WCSl
P.O. BOlt ! 448l!O
Sail Lake Cit),. UI:lh 84114-4880
[phone]
(801) 538·6715 Fax
[phone] T n.D.
WW\ ... L1~'-I.SlillC_lIl.U$ Web
Dect;mbeI 7> 1999
M, Lindsay Ford
Parsons, Behle and Latimer
One Utah Center
201 South Main Street
Suite 1800
Post Office Box 45898
Salt Lake City. Utah 84145-0898
RE: Protocol for Determining Whether Alternate Feed Materials are Listed Hazardous
Wa.stes
Dear Mr. Ford:
On November 22, 1999, we received the final protocol to be used by International Uranium
Corporation (IUSA) in determining whether altemate feed. materials proposed fol' processing at
the White Mesa Mill are listed hazardous wastes. We appreciate the effort that went into
preparing this procedrue and feel that it will be a useful guide for {USA in its altemate feed
determinations.
As was discussed, please be advised that it is IUSA's responsibility to ensure that the alternate
feed materials used are not listed hazardous wastes and that the use of this protocol cannot be
used as a defense if listed hazardous waste is somehow processed. at the White Mesa Mill.
Thank. you again tor your corporation. If you have any question!;, please contact Don Verbica at
538-6170.
Sincerely,
~ qj7t: -.'~" ....
. 'd// /~.,U • : ' . .1-~J ~ . '~'~'-""'" /if;.,./.. ,,~~ ennis R. Do, 15, ~ecutive Secretary
Utah Solid and Hazardous Waste Control Board
c: Bill Sinclair. Utah Division of Radiation Control
F. \sHw\HW!3\DVERBl(:"'\WI"''''hil<:~,\Vpd
w •.••••.•••
1.
PilOTOCo4 lipn J.)ETERM~rrNG WHETHER
ALTER."'JATE FEED MATElUALS ARE LISTED HAZARDOUS WASTESl
I l ';
NOVEMl3ER 16;:1999
SOURCE INVESTIGATION. I ;t
l
; :
I ; i
Perform a good faith irrvestigatipn r(a "Source Investigation" or "Sl")2 regarding whether
any listed hazardous wastes3 <lI'k Ibcated at the site from which alternate feed. material4
("Material") originates (the "Sit~")i This investigafion will be conducted in confotnlaIlce
with EPA guidances and the! ektellt of info~lation required will vary with the
circumstances of each case. ~oll;owing are ex~ples of investigations that would be
considered satisfactol)' under lEP A guidance and this Protocol for some selected . . /,., sItuations: t :
• Where the Material is dt has been gene~ated from a known process under the
control of the gC11Cl..Jo~t (a) an affida~it, certificate, profile record or similar
document from the den~ator or Site ~anager, to that effect, together with (b)
a Material Safety o;a~ Sheet ("MSD~") for the Material, limited profile
, I i
i I I f ~ :
1 This Protocol reflects the procedures tJiat~will be fOl1ow~~ by QR iHKlefStanaiag ~e~\,"9: tRe Utah
Dp,ri&ieR Elf ~e)j~ eftd Ua~e\llS wasta, Deiertmem ef 1S&Yi!:eameete~ QwHi~BQ" ~e "State·')
&ad International Uranium (USA) CQrp6rJtion ("ruSA"); for determining whether alternate feed I 1_ ...
materials proposed for processing at the Wjbi~ Me.sa Mill are; (or contain) listed hazardous wastes. It is
based on current Utah and EF A rules and Eo?A guidatWe under!the Resource Conservation and Recovery
Act ("RCRA"), 42 U.S.C. §§ 6901 et seql inns Protocol wQl ~ ohanged as necessary to reflect any
pertinent changes to RCRA rules or EPA ~~ce. ~ ;
I . I
2 This investigation will be performed by rosA. by the eu~ responsible for tIle s~te from which the
Material originates (the "Generator"). orb~ a hombirlstion of~~e two.
3 Attachment 1 to this Protocol prOvidJ.8 'summary of tb.~1 diffel·~t classifications of .R.CRA listed
hazardous wastes. , ~
4 Altemate feed materials that are primary r .intermediate produots of the generator of the material «(!.g.,
··green" or "black" salts) are not RCRA .. ecbndary materials'~ or "solid wastes:' as defmed in 40 CFR
261, and are not covered by this prorocol./ r : I
5 EPA guidance identifie~ the fonowina sOurces of site~ and waste-specific information that may,
depending on the circumstances, be cons\ddcd in such an i~vestigation: hazardous waste manifests,
vouchers, bills of lading, sales and invtt9IY records, mat~al safety data sheets, storage records.
sampling and analysis reports, accidentr n..-ports, site! ,investigation reports, interviews with
employees/former employees and fonner ofners/opcrators. ;spjU reports, inspection reports and logs,
permits. and enforcement orders. See e.g., IIFed. Reg. 18805 ~Apri129. 1996).
1 :
!
J03961.l r
}'ROTOCOL FOR D£TERMIN[;'IiG WUiTHER ALTERI"IATE l~£O MATERIALS ARE LJST£D HAZAIl.OOUS W~ES
1· . 1 II .'. d . d b h I samp mg, or a matena COlllpOSltl0n etemllne y t e generator: operator
based on a process material b~ance. j'
• Where specific utformation'! exists about the generation process and
management of the: Material~1 (a). an affidavit, certificate, profile r<~!;;ord or
simiJardocu.mr,mt from the oJpera~Qr-01' Site M!lJ1ager. to that effect, togather
with .(b~ ~ MSl?S .for the l~aterial. ]~ted profile sampling data or a
preextstmg mvesbgauon perf~r.tned at the S te pursuanr to CERCLA. RCRA
01' otbe.t -state or federal envi.ro~menta1laws or p~ograms.
I.
• Where potentialJy listed proceSses are known to have been conducted at a Site,
an investigation considering ~:the following sources of information: site
investigation reports prepared ~der CERCLA. RCRA or other state or federal
environmen:tal1aws orpro~ (e.g .. all RIlFS, ROD. RFI/CMS. hazardous
waste inspection repon); intez1yie\vs with persons possessing knowledge about
the Material andlor Site; and review of publicly available documents
concerning procesS activitie~ or the history of waste generation and
management at the Site. I·
!:
• If material ftom the same s~i.u-ce is being or has been accepted for direet
disposal as lle.(2) byproduc~i materia! in an NRC-regulated facility in the
State of Utah with the consenllor acquiescence ofthe State of Utah, the Source -I
Investigation performed by such facility.
Proceed to Step 2.
I, I'
!:
2. SPECIFIC INFORMATION ORAGREEMENTIDETERMINATION BY
RCRA REGULATORY AUTHORlTY] THAT MATERIAL IS NOT A
303961.1
LISTED HAZARDOUS WASTE? i: . --
::l. Determine whether specific jnformatio~ from the Source lnvestigation exists about the
generatirm and managCinent of the Matedal to support a conclusion that the Material is
not (and does Dot contain) any listed!!hazardous waste. For example, if specific
infonnation exims that the Material was ilot generated by a listed waste source and that
the Material has not been mixed with any!iisted wastes, the Material would not be a listed
hazardQUS waste. ~:
h. Alternatively. determine wh.ether the abptopriate state or federal authority with RCRA
jurisdiction over the Site agrees in writi~g' with the generator's determination that the
i:
I ,
"
I: I· t' i:
!!
I~ I! 2!~
I; •
w •.• ~ •.••• I
l)ROTOC'Ol. fOR 1) tTERMlNING Wn E"fU ER AI, TF,RNATf. l~U:O MA l"ERIJ\l~S ARE LISTED HA7.A RDOUS WASTES ,
i
1 I.
1 r li
Material is not a listed haiardous waste, has madb a "contained-out" detemlination6 with
respect to the Material or ~s concluded the Mateilial or Site is not subject to RCRA. i I : it If yes 10 eith.er question, p'joceed to Step J. : !I
If no to bot" questions, prate&! to Step 6. ; II
3. PROVIDE INFORMAT10N TO NRC ~ J! AM.
1 I .• I
a. If specific information bts to suppo~ a ~D,clusiOll that the Material is not, and does
not contain,. any l~sted ~,aza:-d~us was~e. f$teWal;iGli . . . • .'
~IUSA~ WIll provIde a d~nptl0n of tIle: So~c~ Inveshgatlon to NRC and/or the State:
of Utah Department of Edvironmeutal Q~alitY, Division of Solid and Ha7..ardous Waste
(the "State"), together willi an affidavit eXIHailling why the Material i$ not a listed
hazardQUS ~ast~ . !. I ; I'.. _ . . .
b. Alternatively, if the-appropnate regu~tory!au~onty Wlth RCRAJIUlsdlctIOn over the
Site agrees in writing witli the generator's de\enJmation. that the Material is not a listed
hazardous waste, makes a bontained-out deterinui~tion or determines the Material or Site
is not subject to RCRA, rosA will pro'Vidl;: docUb.entation of the regulatory authority's
determination to NRC an\! the State. rUsAlm* rely on such detemtination provided
that the State agrees the cobclusions of thq re¢a(chry authority were reasonable and made
in go.ad faith. I. !II
Proceed to Step 4.
I I :
----------------------. 'I
6 EPA explain' the "contained ...... " (iJso ref .... d to ~s .. c~nta~.d-in .. ) principle as fullow",
In practice, EPA has applied ~h<:! corttained-inlptin~ipl~ to refer to a process where a site-
specific determination is made that cQncenfra~ODS of~dous constituents in any given
volume of environmental media are low endugh :ro determine that the media does not
"contain" hazardous waste. i Typically, thes~ so-caU~ "contained-in" [or "coxuaiued-
out"j detenninations do ndt mean that n~ h~us constituents arc present in
environmelltal media but simply that the IconcODtIktions of hazardous constituents I . . II
Present do Dot warrant ttl11Ilat'rement of the medla as ~dQUB waste. _ ..
b I .' II
EPA has not, to dat~, issued ~efinitive gtridaJce'to establish the concmtrations at which
contained-in detenninatiQns tP.ay be made. As noted ~bovc. decisions that media do not
or no longer contain hazur~OU8 waste are l typicall~ made on a cll$e-bY-¢a:5c basis
considering the risks posed by' the contaminated media!
63 Fed. Reg. 18619·, 28621-21 (May ~6, 1998) (Phase!W I~O~~Ieamble).
I
)0)961.1 3
!
l'ROTOCOL fOR Dt::·C£Jl.MININC WHF.TH~R ALTEll.l"'lATE FEED MATJ:':RIALS ARE LIS'fEO HAZAROOt.;S WASTE's
4.
5.
6.
303961.1
1;
'I . ) ·1
DOES STATE OF UTAH AGREE THAT.u.U1pREVIOUS STEPS HAVE I BEEN PERFORMED IN.ACCORDANCE WITH THIS PROTOCOL?
I 'j : I .
Determine whether the g:tate agrees that :ttUs .;frotocol has been properly followed
(including that proper deCisions were mad~ jat ~ch decision point). The State shall
review the information provided by roSA in~Step'~ or 16 J:JfOR\~tly with reasonable speed
and advise JUSA if it b'elieves ruSA wlsl nqt properly followed this Protocol in
determining that the Material is not listed haiJ.do~B waste, specifYing the particular areas
of deficiency. : I ';1
I '
If this Protocol has not been properly fQllow~ by!rUSA in making its determination that
the Material is not a listed hazardous wiste, then !USA shall redo its analysis in
accordance with this Proto901 and, if justified, ~~bmit the infonnati~n descnbed in Step
3 or 16 exp1a.ining why the Material is not a lis'ted hazardous waste. The State shall "I ..
notify ruSA ~r9mf3t!y with reasonable speed ~f ~e State still believes this Protoco 1 has
not been followed. I I ::j
I :1 If yes, proceed to Step 5. ~ I . i
; I .. If 110, proceed to Step 1. ~ i ':;
MATERIAL IS NOT A LISTED llAZARDOUS WASTE.
The Material is not a listed hazardous wasiel J no further sampling or evaluation is
necessary in the following circumstances: I I :ll
• Where the Material. is d.etemrinedlnot to be a listed hazardous waste
based on specific information abo~t th~; generation/management of the
Material OE. the. appropriate RCRA! regUlatory authority with
j'llrisdiction over the Site agrees ryth th~ generator's detennination that
Ihe Material is not a listed HW. maies.~ contained-out detemrinatioD.
or concludes the Material or Site ~s hot ~i;ubj ect to RCRA (and the State
agrees. the eoncl~sions of the reg~a\()~1 authority were reasonable and
made In good faIth) (Step 2); or i I :1
+ Where the Material is detennined:npt tq be a listed hazardous waste (in
StepS 6 throllgh 11, 13 or 1 S) andjCp~mationiAcceptancc Sampling
arc determined not to be necessary ('lln4cr Step 17).
IS MATERIAL A PROCESS WASTE ~d~ TO BE A LISTED
HAZARDOUS WASTE OR T.O "BE MIXliD WITH A LISTED
HAZARDOUS WASTE?; i I ::/ ! I ,!
Based on the Source Investigation, determiP~ w~ether the Material is a process waste
known to be a listed hazardous waste or to be thlxc;:d with a listed hazardous waste. If the
Material is a process waste and is from a iiJte.d;' hazardous waste source, it is a listed
:' I:;
.' 4 1 :i
:i I
w .... " .• " ••.
PROTOCOl, FOR DETERM1~lNC WUETHER AL:n:lt"lAn~ FEEl:! MAT£RI/,LS ARE LISTED HAZARDOUS WAST ES
i '
t
hazardous waste. Similarly, if tile ¥aterial ~s ~ pi-6c~ss waste and has been mixed with a
listed hazardous wastc, it is a listed,hazardo*s!waste under the RCRA "mixture rule." If
the Material is an Envirorunental Medium,? ii cannot be a listed hazardous waste by direct
listing or under the ReRA "miXture rule."s /if the Material is a process waste but is not
known to be front a listed source or to be m'xM with a listed waste, or if the Material is
au Environmental Medium, proceed to 8t s through 11 to determine whether it is a
listed hazardous waste.' ;i
If yes, proceed to Step 12 .
./fllo. proceed to Step 7,
, , ,
7. DOES MATERIAL CONTAI~ ANY PO~~NT~LY LISTED
HAZARDOUS CONSTlTUE~S1 II '~
Based on the Source Investigation (and, if !:ipplicable) Confirmation and Acceptance
Sampling), deternrine whether the Material ooritains any hazardous constituents listed in
the then most recent version of 40 CFR 26,. \APpendix . vn (which identifies hazardous
constituents for which F-and K-Iisted wastes were listed) or 40 CFR 261.33(e) or (t) (the
P and U listed wastes) (collectively "Potentiktiy Listed Hazardous Constituents"). If the
Material contains such constituents, a sourcJ evaluation is necessary (PUISU8nl to Steps 8
through 11), If the Materiai does n.Q1 ~JDtain any Potentially Listed Hazardous
Constituents, it is not a Hsted h~ardous I'aste. TIle Material also is not a listed
hazardous waste it where appli~bleJ Conf~ti.Qn and Acceptance Sampling results do
not reveal the presence of any. '''ne\v'' Potdntially Listed Hazardous Constituents (i.e ..
constituents other than those :that have +i already been identified by the Source
Investigation (or previous COnfirmatiOnlA1c~ptance Sampling) and determined not to
originate from a listed source). . I ;
If yes, ptoceed to Step 8.: :
If no, proceed to Step 16.
"
,1
7 The term "Envirorunental Media" means'soils, groWld 9~ surface water and sediments.
8 The "mixture rule" applies only to' m.ixtUres 'of listed ~~ous wastes and oth.er "solid wastes," See
40 CFR § 26L3(a)(2)(iv). The mixture rule does', ~1 :apply to mixtures of listed wastes and
Environmental Media, ba;ause Enviionm~l1tal Media a 'c: not :'soHd wastes" Wlder RCRA. See 63 fed.
Reg. 28556, 286Z1 (May 26,1998).: j
1
,!
"
303961. t 5 I
u ... " ..... ~ ~ .. • :.. ~t. • ~ .\ '"
PROTOCOL fOR DETERMININC WH€THER ALH:RNATF. Ff;tD MATERrALS AR£ LlSn:o HAZARDOUS WAST£S
8.
9.
~ .
IDENTIFY POTENTlALL Y I,ISTEO WASTES. I . 1
j !
IdentitY potentially listed hazard9us wasteS ("Potentially Listed Wastes") based on
Potentially Listed Hazardous Constituents detectca in the Material, i.e., wastes which are
listed for any of the Potentially Ustd Ha7..a.rdous ~onstituents detected in the Material, as
identified in the then most current version ,of 40 CFR 26 i Appendix vn or 40 CFR
261.33{e) or (£).9 ~th respect tolPotentially Li~ted Hazardous C~nst~tuents identified
through COll.fimtatlon and/or Acceptance Sampling, a source evaluation (PUlSnatlt to
Steps 8 throngli 11) is nec.esscb only for ,!'-'new" Potentially Listed Hazardous
Constituents (i.e.. constituel1ts othJr fum those that have ~ already been identilied by
the Source lnvestigation (or previous ConfumationlAcceptance Sampling) and I .
determined not to originate frOIn a listed source). ; 1 .
Proceed to Step 9. i:
WERE ANY OF THE POTENTIkLY LISTED WASTES KNOWN TO BE
GENERATED OR MANAGED AT SITE? -!
I [. "
Based on information from the Source Investigation, detemrine whether any of the
Potentially Listed Wastes identifirid in Step'8 are known to have been generated or
managed at the Site. This deteoni~ation involves ~ideJ]tifying whether any of the specific
or non-specific sources identified irl. the K-or'F~lists has ever been conducted or located
at the Site, whether any waste froth such processes has been managed at the Site, and
whether any of the P-or U-listed l commercial chemical products has ever been used,
spilled or managed there. In pal[ticular, this determination should be based on the
following EPA criteria: ! :
Solvent Listings (Fool-FOOS) I
Under EPA guidance, "to dJtermine if solvent constituents contaminating a waste I . are ReRA spent solvent FOQl-FOOS wastes, the [site manager] must know if
I' -0
• The solvents are spent imd cannot: be ,reused without reclamation or
cleaning. L· :!
I· l
• The solvents were lIsed exclusively/or their solvent properties.
I '
• The solvents are spent nibcfures and blends that contained, before use,
a total of 10 perce/It at more (by v~!ume) of the solvents Listed in
FOOl, F002, F004, and Fp05. '
i
i. i . 0 • ~ 1· ,.
9 For example. if the Material contains tetrachloroethylene, the foJlowing would be Potentially Listed
Wastes: FOOl. F002, F024. K019. K020, K1Sd,'K151 or U210! Sll2 40 CFR 261 App. VII,
I. ' I
!'
I: ,I
II 0' j o "
w y , " • ~ -.... I
•••• " •• I.
PROTOCOL. yoa DETERMINING WHETHER A~ Tf:j' 'A 'rE ~E'::D 7" tEIUALS AR£ Llsn;o fiAlAJU)ouS WASTES
I ., ;1 • . i"
If the solvents containM in tbe lwasteSj are ReRA listed wastes, the
[wastes] are ReRA hazkddus waste. : 'A{Jlen the [site manager] does not
have guidance infunn~oh on the; use 'of the sol'Vents and their
characteristics before usb, ilie [wastes] :c~ot be classified as containing a
listed spent solvent"'O i Th~ person perf~rming the Source Investigation
will make a good faith ~ffoh to obtain infurmarion on any solvent use at
the Site. If solvents were Jsed at the Si-tl;, general industry 5tmldards for
so1vent usc in effect at the time of ll§6 will be cOnsidered in determining
whether those solvents Contained 10 pe(~ht or more of the solvenm listed
in FOOl. F002. F004 or FaDS. i r I I I I ~ {(-Listed W astes and F-Listedl Wastes Other T h an F001-FOns I .r ! !' Under EPA guidance, to detemrine whether K wastes and F wastes other than
1 • I' FOOI-FOD5 are ReRA usteO wastes, the generator "must know the generation
process information (ab6ut Jach waste bntained in the RCRA waste) described in
the listing. For exampl~ fo~ [wastes] to ~'e identilied as containing KOOI wastes
that are described as 'botlorlt sediment sliidge from the treatment of wastewaters fr~m wood preserving pfoc~es that u~e F Bosote and/or pentachlorophenol,' the
[sIte manager} must know !he manufacttmng process that generated the wastes
(treatment of wastew.aters fi'~m wood prdemng process), feedstocks used in the
process (creosote and PimtachlorophenolJ; and the process identification of the
wastes (bottom sedimentl sl~).'·ll .! ';
! J . ! I p-and U-Listed Wastes ! : : I :
J • i I
EPA guidance provides ;tha;· ''P and q ,~tes cover only unused and unmixed
commercial chemical prod pts, particU:.laily spilled or off-spec products. Not
every waste containing a P ;or U cherqiJ,I is a hazardous waste. To d6temrine
whether a [waste] contains ~ P or U wast~, the [site manager] must have direct
evidence of product us~_ Ih particul~> I e [site manager] should ascertain, if
possible, whether the ~hepUclus are: I \
• Discarded (as described ~ 40 CFR ~6 ~2(a)(2». 'I . -I I
• Either off-spec commercia) prOd1.1cts 0 :a commercially sold grade.
'! :
I I
i
I
10 Management of Investigation-Derived \Vastes During Site fuspeotions, EPAl540/G-911009. May 1991
(empha$is added). :.1 :: 'I II
Il Management of Investigation-Derived Wastes D~g s-g.e Ul:'!p¢ctiOJ1S, EP Al540/(1...9 1100 9. May 1991
(emphasis added). ,j I ~
i:
'H\11\~1 ,
., " ~ ~! Ii
W I .-...... ~ , •••
l)(lOTOCOJ" FOR Df.TEtl.'I1SNI:'lG WHF,THER AI. TER."Ilb. TE FEED M,\ TF.RIALS ARE LIS'(t:l) HAZARDOL'S W ASTI:S , .
:I j ij:
• Not used (soil contamitt~ ed J ith spilled unused wastes is a P or U
waste). 1 I , jl!
• Tb. sole active ingredi!lllt in a ~rrnul1on.""
!'Ihe ~ .!I!i~~s.-W;<'9tential1X Li.rted Wastes Yill" m own
to be genel'attXi or managed ~t the Site. I furtherl' evaluation is necessary to determine
whether these wastes were disposed of or; commip.gled with the Material (Steps 10 and
possibly 11). If t*e &B5'iYeF is fle7~If PotentiallY! Listed Wastes were not known (0 be
generated or managed at the Site, rl\e.n information concerning the source of Potentially
Listed Hazardous Constituents in I the Matcri~ will be considered "unavailable or
inconclusive" and, under EPA guidance, lJ !the Material will be assumed not to be a listed
hazardous waste. i
'i
I I ,. . I,
12 Milmlgeme:at of :Investigation-t>eriv¢d W~~ qUrit;).g Site Inspections, EPA/540/G-9lf009, May
1991. ;1 I l
13 EPA guidance consistently provides tha~ ,hereu1uonnati~n cooceming the. origiIl of a waste ,is B9!
illlavailable or inconclusive. the waste may be assumed not to be a listed hazardous waste. See e.g.,
Memorandum from Timothy Fields (Acting .fAssistant A.d.J:ninistrator fef Solid Waste & Emerg{!llcy
Response) to RCRAICERCLA Senior Policy frranagbrs regaAling "Management of Remediation Waste
Under RCRA," dated Qctober 14, 1998 ("Whi;r~ a facility ofner/operator makes a good faith effort to
dct:e.rmine if a material is a listed b~dou:J wastci but C'.umot make such a dcterroina1ion. because
documOt'ltatiol1 regarding a source of o0r+mina.tio~ cohtaminant, or waste is unavailable or irlcollcJ~'II~. ~PA has stated that one may assume the s09rce, e,ontaminant, or Waste is not listed ~rdol\S wast:en); NCP Preamble, S5 Fed! Reg. ~ 8758 (March 8, 1990) (Noting that "it is often
necessat)' tolcnow the origin of the wasre tol deterririne wh6ther it is a listed waste and that, if such
documelltation is lacking. die lead agency may assufne it is hot a listed waste)j Preamble to proposed Haz~dous W~~e Identification Rule, 61 Fed~ Rt..-g, 18805 (April 29~ 1996) \,Faciti1;y own¢r/opcrators
should make a good faith effort to deternHne '\\j'hetheJ:/mcdia \~ oon:tBminntcd by hazardous wastes and
ascertain the &rtcs of placement. The AgenC~ believes that by using available site-~ wasre·speoific
information _ .. facility owner/operators wou1d;~icailybe ab\eto make these detenninatiQos. Howevea:, a~ discussed earlier in. the ptea.mble of today's propo~sal. if ilijormatkm Is ,wI available or ilIC(lllciusiYe,
facWry owner/operators may generally assurhe [llal lite material c01Uamillaling Llie media were not I • " . h.azo.rdolls wastes."); Preamble to LDR Pluis¢ N iRule, 63 Fed. Reg. 28619 (May 26, 1998) ("As
discussed in the April 29, 1996 proposal, tbJ Agdny eontipueS' 00 believ~ that, if iliformatroll is /WI
available or inconclusive, it is generaily reasbnable: to asslljlle'that contaminaled soils do not contain J I .~, untrea.led hazardous wa.'ues .,. "); and MtITlI~ran~ from '0hn H. Skinner (Director, EPA Office of
Solid Waste) to David Wagoner (Director. EPA A~r and vraste Management Divi$ion, Region VU)
regarding "Soils from Missouri Dioxin SitJs," da~d J~~ 6, 1984 ("The analyses indicate the
presence of a number of tox.ic compounds. in many of 'tltc soil samples taken from various sites.
However, the presence of these toxicants in the s~i1 ao~s [' ot automatically make the soil a R.eRA
(footnote continued on uext page) I ;:
: 1 1: .
j 0 I'
¥ROTOCOL FOR OETERMINI~G W HETJIER ,\1. TERNATE l<"EED ~A.T£RIALS A.R£ LIS'fED ILUA.RDOU$ WASn:s
10.
11.
12.
J' :Ii ~~ , :11 ~.1 I ·~t
,f:,' f,: ~I
! ~l i I,: I , il! ;' : ,!: 'I!
/fyes, proceed to Step 10.
If no, proceed to Step 16,
WERE LISTED WASTES KNOWN TO BE DISPOSED OF OR
COMMINGLED WlTH MATE~? i ~l , j!
If listed wastes identified in St~ ~ were~ J.~wnl ito. be gene~ted at the ~ite7 detelUline
whether they were known to be ~JSP.~5ed o.f1f CO~l.D.gled wlth the Matenal?
If yes, prOc£ed to Step 12. ,'~! 11
lfno, proceed 10 Step 11. ; ~ l~
ARE THERE ONE OR MORE PrTE~~ ~.~ON-LISTED SOURCES OF
LISTED HAZARDOUS WASTE CONSTI'fUENTS? : Ii I,
In a situation where P:,tentia1:1y L~te~ "'iastes were known to h~ve been
generated/managed at the SIte, but jthe wast~ werp not known to have been dlsposed of
or cOITllIlingled with the Material, detcimihe J..bcther there are potential non-listed
sources of Potentially Listed H~dous Co~Stitu&nts in the Material. If not, unless the
State agrees otherwise, the ~ns~~nts; Jtll b#. ~sumed to be from listed sources
(proceed to Step 12). If so, the ~~terial:w~p bil ~sumed not to ~e a list~ hazardous
waste (proceed to Step l6). NotwrtQstand.Vla:ithe 6?,lstence of potential non-listed sources
at a Site, the Potea.tially Listed Hazrdou.s:dhs'tithcnts in the Material will be considered
to be from the listed source(s) if, qas,ed ~n the r~ative proximity of the Material to the
listed and non-listed soulce(s) aud10r infoIIfRtioni concerning waste management at the
Site, the evidence is compelling tbat the list -sowlce(s) is the source of Potentially Listed
Hazardous Constituents in the ,Ma:teijal. .
"
If yes, proceed to Step 16. I
If ,to, proceed to Step 12. I: i r ! ~ t I !
MATERIAL IS A LISTED HAZFOPS;~~TE.
-. . I ! TI'le M. aterial is a list.ed hazardous laste midJ~ theifollowmg circumstances:
(footnote contiDued from previous page) ': ; ',: ;
, I it I' ,-r
Mzarda.u,1 waste;, The origin of tb.e tox.i~ts ~ust be~krf~wn ~ order to determine that they are derived
from a listed hazmfons waste(s). q the exact: origin' ofl.l~lte t~xfuan($ is not mowl1. Ihe soils cannot be.
cons-itkred RCRA IIQZw'dous wastes unless '~ exlu~it ?I1C i more of the characteristics of hazardous
warne ... j. I :;
I I
I:
.1 'I
lO39{i1 .1 9 I " I ,
! il 'i
•• ~." ~ y ,I II
,
"
PROTOCOL "OR D£TER. ... SI'IING WlIU'lt£R Al:rtRNATF. FEE~ MA t RIALS ARE Lrsn:D llAZARDOUS WASTES
, !II
• If the Material is a process waste and i~ known to be a listed hazardous . ~: wa5te or to be mixed with a listed hazat<ious waste (Step 6),
t If Potentially Listed Waste~! w~1"e lmown to be 3stuaUy
genccated/managed at the Site and to ~;e disposed of/cotluningJed with
the Material (Step 10) (~ubject to a «cl:ontained.-out" determination in
Step 13), or :: I
r
• If Potentially Listed Wastes' We.t5 known to be asmally
generated/managed at the Site, we, not known to be disposed
oUcommingled with the Material but there are not any potential non-
listed sources of the Potentially ~isted Hazardous Constituents
detected in the Material (Step 11) '(subject to a "contained-out"
determination in Step 13).
Proceed to Step J 3.
13_ HAS STATE OF UTAH MADE A CONTAINED-OUT DETERMINATION.
30)961.1
If the Materia! i. an Environmental McWwn,.and: ~
• the level of any listed waste constitu.entS in the Material is "de minimist• j or
• all of the listed waste constiruents or J~sses thereof arc: already present in the
White Mesa MilPs tailings ponds as l :result of processing conventional ores
or other alternate feed materials in coJceo.trations at least as high as found in
the Materials
I
the State of Utah will consider whether it is p.ppropriate to make a contained-out
detennination with respect to the Materia1.
If the State makl!s a ctJlJtained-otlt determination, f;~oceed to Slip 16,
!fthe Slate does not make a contained-out tietenniilaliO'fl, proceed to Step 14.
:. 11 ~~~~~S~~E~T~=~ATE LISTED HAl' ZARDOUS WASTES
Determine whether there is a reasonable way . IJ segregate material that 18 a listed
hazaxdous waste from alternate feed materials ttkt are not listed hazardous wastes that
will be sent to roSA's White Mesa Mill. For ~xample. it may be possible to isolate
material from a certain area of a remediation site ~d exclude that material from Materials
10
.
,.
i
I ,
! ~ .
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W " f' ....... , ••• • • ~ ., " ~ " >I
,.
PRO'fOCOL FOR DETf:RMIN(NG WHETfIEKALTEI:t."IA',·£ FEED ~J\l[RIAf .. S ME Ll,sTED HAZARDOUS WA.ST~S
that will be sent to the White Mesa Mill. A~tef~ativelY. it may be possible to increase
sampling frequency and exclude materials with {.espeot to which the increased sampling
identifies constituents which Jlave been attri'btiteJito listed hazardous wa.')te.
I I' If yes, proceed 10 Step 15. ; ;
I ,I If no, proceed to Step 12. j II:
[ ~!
15. SEPARATE LISTED HAZARDOUS WASTES FROM MATERIALS.
'\ ~!
Based on the method of segregation detennil,1ed~;under Step 14, materials that are listed
hazardous wastes are sep~ated from Materials th~ w i) be sent to the White Mesa MilL ! ,.,
For materia18 l/lat are listed hazardous wastes, pt,oceed to Step 12.
• 111
For MaJeriais to be .fent to the White Mesa M{ll. kroceed 10 Step 16.
; ~:
16. PROVIDE INFORMATION TO NRC AND utAH.
17.
303'161,1
. j:
If the Material does not contain any PotJuially Listed Hazardous Constituents (as
detennined in Step 7), where information concbi.no-the source of Potentially Listed I 1111 """0
Hazardous Constituents in the Material is "un~va!lable or lnconclusiven (as determined in
Steps 8 through 11), or where the State of Ut~ has made a contained .. out detenninatiou
with rf',spect to the Material (Step 13), the Mai:eri~l will be assumed not to be (or contain)
a listed hazardous waste. In such circumStaJ~es, ruSA will submit the following
* . II' documentation to NRC and the State: ~:
1 I.
• A description of the Source fnvestigatibn;
I I::
• An explanation of why the Materia,! isinot a listed hazardous waste.
: ~
• Where applicable. an explanatio~ o~ why Connnnation/ Acceptance
Sampling has been detennined notlto ~e necessary in Step 17.
• If Confumationl Acceptance samplin~ has been determined necessary
in Step 17 ~ a copy of ruSA's b& the Generator's Sampling and
Analysis Plam. I f:
I r
• A copy of Confirmation and 'A~~tance Sampling results; if
applicable.. rUSA will submit these bswts only if they identify the
presence. of "new'" Potentially J!.i:st~ Hazardous ConstilUents (~
defin~d in Steps 7 and 8). [~!
Proceed to Step 17. I :1;
I m· ARE SAMPLING RESULTS OR DATA REPRESENTATIVE?
Determine whether the sampling results or ~ L the Source Investigation (or. where
applicable, ConfiunatiolJlAcceptance Samplhlg ;~ults) are representative. The purpose
I I
11 I
II
• ....~ v ... ~ '"
i
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PROTOCOL FOR DETERMINING WHETHER AL~tRNt\TF; FEe, M;\~£IUi\(,l'i AllY. I,ISTED RA1,A.RDOUS W A.SUS
,~ I
303961.1
of th.is step ) is to determine whether Gpnfuination and Acceptance Sampling (or
continued Confirmation and Acceptance SampHng) are necessary. If the sampling results
or data are representative of all Material cJ.e§tinedl for the White Mesa Mill, based on the
extent of sampling conducted, the nature ot th~1 Material and/or the nature of the Site
(e.g., whether chemical operations or waste:fusp4sa1 were known to be conducted at the
Site), future Confirmation/Acceptance Sam~ling lwill not be necessary. If the sampling
results are not representative of all MataiaJ. destined for the White Mesa Mill, then
additional Confumationl Acceptance sampl~rg ~ay be appropriate. Confinnation and
Acceptance Sampling will be required only where it is reasonable to expect that
additional sampling will detect addition~ contaminants not already detected. For
example: :1 I
• Where the Material is segregC!ited from Environmental Media. e.g.. the
Material is containe~zed. there ir a ~gh probability the sampling results or
data from the Source Tnve.stigati.on are representative of the Material and
Confirmation! Acceptance Samplfug w6uld not be required.
• Where ruSA will be; accepting JateJl from a discrete portion of a Site, e.g.,
a storage pile or other defined ~ea. ahd adequate sampling characterized the
area of concern for radioactive apd c~emical contaminants, the sampling for
that area would be considered ~epreSentative and ConfiunationiAcceptance
sampling would not be requix-ed. ·1 1
• Where Material will be receivedl fro~' a wide area of a Site and the Site has
been carefully characterized for·1 radioactive contaminants, but not chemical
contaminants, Confumation! Acceptancie sampling would be required. ·1 I
• Where the Site was not used for ~duJnial activity or disposal before or after
uranium material disposal, and tlie Site has been adequately characterized. for
radioactive and chemical contahnnahts, the existing sampling would be
considered sufficient and Con1ii!mati~)fl1 Acceptance sampling would not be
required. _ :\ I
• Where listed WQStes were lrnown to beldisposed of on the Site and the limits of
the area where listed wrtes: were managed is not known,
Confirmation/Acceptance Sampli;tlg v{ould. be required to ensure that listed
wastes are not shipped to ruSA (~ee S~ep 14).
If yes, proceed (0 Step 4. J I
If 110, proceed to Step 18.
,I
12 l
I
, I
.• ~ ,. '* ., ....
. ,
.PROTOCOl. fOll. DETERMINING WH£Tll£R ALTERNATE FEED MA'I'E!IU..c\LS ARE LISTED HAZA1tOOUS WASTES
18. DOES STATE OF UTAH AGREE THAT 1ALL PREVIOUS STEPS HA'VE
BEEN PERFORMED IN ACCORDANCEl WITH THIS PROTOCOL?
Determine whether the State agrees that this Pro1ocol bas been pIQperly followed
(including that proper decisions were madd at each decision point). The State shall
review the informa..ioI:1 provided by ruSA in:Step 16 J:We1Bf)~ vnth reasonable speed and
advise roSA if it believes ruSA bas not pro~ly followed this ProtQcol in determining
that th~ Material is not listed hazardous I waste~ specifying tQt> partioular areas of
deficiency. !
Iftrus Protocol has not been properly fol1ow~d by ruSA in making its determination that
the Material is not a listed. hazardous wa~te, then roSA shall redo its analysis in
accordance with this Protocol and. if justifie4, resubmit the information described in Step
16 explaining why the Material is not a listpd hazardous waste. The State shall notify
roSA I*6Iflptly with r9§onable speed if the State still believes this Protocol bas not been
I followed. ./
Ijyes, proceed to Step 19. I
If no, proceed to Step 1. 'J
19. MATERIAL IS NOT A LISTED HAZARDOUS WASTE, BUT
I CONFIRMATION AND ACCEPTANCE SAMPLING ARE REQUIRED.
The Material is not a listed hazardous Waste,!but Collfirmation and Acceptance Sampling
are required, as determined necessary under Step 17.
I
Proceed to Step 20. !
!
I
20. CONDUCT ONGOING CONFIRMATION AND ACCEPTANCE
S~L~G. !
Confirmation and Acceptance Sampling . vilt continue until determined no longer
necessmy under Step 17. Such sampling will be conducted pursuant to a Sampling and
Analysis Plan ("SAP") that specifies the frl:,quency and type of sampling required-If
such sampling does not reveal any ~'new" pbtentially Listed Hazardous Constituents (as
defined in Steps 7 and 8), further evaluatiod is not necessary (as indicated in Step 7). If
such sampling reveals the presence oflCnew"i constituents, Potentially Listed Wastes must
be identified (Step 8) and evaluated (Steps 9 through 11) to detennine whether the new
constituent is from a listed hazardous waste ~ource. Gcnerally~ ill each ease, the SAP will
specify sampling comparable to the level ~d frequency of sampling performed by other
facilities in the State of Utah that dispose ofl l le.(2) byproduct material, either directly or
that results from processing alternate feed materi al's.
Proceed to Step 7.
,!
I
'i I
.!
1 ~ I
......... , .t.,
i !
Attachment 1 I
Summary of ReM Listed Hazardous Wastes : ,
There are three different categories of listed ~azardo~ waste under RCRA:
• F-mted wastes from non-specific sour.ces (40 CFR § 261.31(a)): The&e wastes
include spent solvents (FOOI-FOOS), sp~cified wastes from electroplating operations
(F006-F009), specified wastes from metal heat treating operations (F010-FOI2),
specified wastes from chemical 'conversion coating of aluminum (F019). wastes from
the production/manufacturing of speCified ehlorophenols, chlorobenzenes, and
chlorinated aliphatic hydrocarbons (f019-F028). speCified wastcs from wood
preserving processes (F032-F035), specified wastes from petroleum refinery primary
and secondary oil/water/solids separation sludge (F037-F038), and leachate resulting
from the disposal of more than one listed hazardous waste (F039).
• K-listed wastes from speciftc sources (40 CFR § 20J.32): These include specified
wastes from wood prese(Vation, inorglmic pigment production. organic chemical
production, chlorine production, pesticide production. petroleum refining, iron and
steel production, copper production, primary and secondary lead smelting, primary
zinc production, primary aluminum r.ed.uction, fe11'oalloy production, veterinary
pharmaceutical production, ink fonnulat~on and coking.
• p. and U-listed commercial chemical p,roduc13 (40 CFR § 261.33): These include
commercial chemical products, or manufacturing chemical intennediates having the
generic name listed in the uP" or uU" lil't of wastes, container residues, and residues
in soil or debris resulting from a spill of these materials. I "The phrase 'commercial
chemical product or manufacturing chemical intemlediate ...• refers to a chemical
substance which is manufactured or formulated for commercial or manufacturing use
which consists of the commercially pure grade of the chemical~ any technical grades
of the chemical that are produced or marketed, and all fonnulations in which the
chemical is the soLe active ingredient.. It does not refer to a material, such as a
manufacturing process waste, that contains any of the [P~ or U·listed. substances].,,2
Appendix VII to 40 CFR part 261 identifies thc haZardous constituents for which the F-and K-
listed wastes were listed. . .
. . . .
I
1 P-listed wastes are identified as "acutely iuwu'dous 'wastes" and are subject to additional management
controls under RCRA. 40 CFR § 261.33{e) (1997). U~listed wastes are identified as "toxic wastes.: Id. , I § 261.33(f). : : .
240 CFR § 261.33(d) note (1997).
Protocol for Determining if Alternate Feed Material is a listed Hazardous Waste
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ATTACHMENT 4
Review of Chemical Contaminants in SFC Uranium Material to Determine the Potential
Presence of RCRA Characteristic or RCRA Listed Hazardous Waste
Technical Memorandum
To: David C. Frydenlund
Company: Qenioor::l MiAesEnergy Fuels Resources
(USA) IncGe$.
Re: Review of Chemical Contaminants in
Sequoyah Fuels Uranium Material to
Determine the Potential Presence of RCRA
Characteristic or RCRA Listed Hazardous
From: Jo Ann Tischler
Date: Deoember 15, 2011 July 15,
2013
Waste Project #: ----------------------CC:
1.0 Introduction
This report summarizes the characterization of the Sequoyah Fuels Corporation ("SFC")
Uranium Material (the "Uranium Material"), also referred to as the dewatered raffinate
sludge to be transported from the SFC Gore, Oklahoma facility, to determine whether or
not the Uranium Material is or contains any listed or characteristic hazardous waste as
defined by the Resource Conservation and Recovery Act ("RCRA"). The results of this
characterization will provide information for GOAiseA--MiResEnergy Fuels Resour-ces
(USA) ~Inc. ("DenisonEFRI") to determine the requirements necessary for an
amendment to its White Mesa Uranium Mill ("Mill") State of Utah Radioactive Materials
License No. UT1900479 (the "License") to permit the processing of the Uranium Material
as an alternate feed material at the Mill.
In accordance with the definitions in the Atomic Energy Act, as amended, and 10 Code
of Federal Regulations ("CFR") 40.4, ores with natural uranium content of 0.05 weight
percent or higher are classified as source material and, as per 40 CFR Part 261.4, are
exempt from regulation under RCRA. As summarized in the Radioactive Material Profile
Record, the Uranium Material has a uranium content of approximately 0.7 to 1.0 dry
weight percent natural uranium (0.8 to 1.2 weight percent U30 S). This Uranium Material
is therefore source material, and is categorically exempt from RCRA.
Further, the Uranium Material has also been classified as 11 e.(2) byproduct material by
the U.S. Nuclear Regulatory Commission ("NRC") under SFC's License Amendment 29,
dated December 11, 2002, and for this reason also is categorically exempt from RCRA
under 40 CFR 261.4. Although the Uranium Material is exempt from regulation under
RCRA, Denison EFRI nonetheless requires a due diligence evaluation of potential
materials to be processed, to assess:
1. Whether the material is, or contains, any hazardous constituents that would be
regulated as RCRA listed hazardous waste, if the Uranium Material were not
categorically exempt from RCRA as a uranium ore or 11e.(2) byproduct material
or a categorically exempt solid waste.
2. Whether the material contains any constituents that could generate a worker
safety or environmental hazard under the conditions under which it will be
processed at the Mill.
3. Whether the material contains any constituents that would be incompatible with
the Mill's tailings system.
This memorandum provides the evaluation of the regulatory status of the Uranium
Material relative to RCRA. Evaluation of potential safety and environmental hazards,
and compatibility with the Mill's tailings system are provided in a separate memorandum.
2.0 Site History and Background
The SFC Gore, Oklahoma facility (the "Facility" or the "Site") is a former uranium
conversion facility that operated from 1970 to 1993. The facility was constructed and
operated by SFC, as a subsidiary of Kerr-McGee Nuclear Corporation. In 1983 Kerr-
McGee Nuclear Corporation split into Quivira Mining Corporation and SFC, which
maintained control of the Gore Facility. SFC was sold to General Atomics Corporation in
1988 and continued to operate the facility until 1993.
From 1970 to 1993, the facility chemically converted uranium ore concentrates
(yellowcake) to uranium hexafluoride under U.S. Nuclear Regulatory Commission
("NRC") Source Materials License Number SUB-1010. From 1987 to 1993, the facility
also converted depleted uranium hexafluoride into depleted uranium tetrafluoride in a
different circuit. The Uranium Material consists only of residuals from the conversion of
natural uranium yellowcake to uranium hexafluoride.
NRC's Alternate Feed Guidance currently provides that if a proposed feed material
contains hazardous waste, listed under Section 261.30-33, Subpart D, of 40 CFR (or
comparable RCRA authorized State regulations), it would be subject to EPA (or State)
regulation under RCRA. However, the Guidance provides that if the licensee can show
that the proposed feed material does not consist of a listed hazardous waste, this issue
is resolved. NRC guidance further states that feed material exhibiting only a
characteristic of hazardous waste (ignitability, corrosivity, reactivity, toxicity) that is being
recycled, would not be regulated as hazardous waste and could therefore be approved
for extraction of source material. The Alternate Feed Guidance concludes that if the
feed material contains a listed hazardous waste, the licensee can process it only if it
obtains EPA (or State) approval and provides the necessary documentation to that
effect. The Alternate Feed Guidance also states that NRC staff may consult with EPA (or
the State) before making a determination on whether the feed material contains listed
hazardous waste.
Subsequent to the date of publication of the Alternate Feed Guidance, NRC recognized
that, because alternate feed materials that meet the requirements specified in the
Alternate Feed Guidance must be ores, any alternate feed materials that contain greater
than 0.05% source material are considered source material under the definition of
source material in 10 CFR 40.4 and hence exempt from the requirements of RCRA
under 40CFR 261.4(a)(4). See Technical Evaluation Report Request to Receive and
Process Molycorp Site Material issued by the NRC on December 3,2001 (the nMolycorp
TERn). As a result, any such alternate feed ores are exempt from RCRA, regardless of
2
whether they would otherwise have been considered to contain listed or characteristic
hazardous· wastes. Since the Uranium Material contains greater than 0.05% source
material, it is exempt from RCRA, regardless of its process history or constituents, and
no further RCRA analysis is required. Further, the Uranium Material has been classified
as 11 e.(2) byproduct material by NRC under 40 CFR 261.4(a)(4). 11 e.(2) byproduct
material is exempt from RCRA, and for this reason also the Uranium Material is exempt
from RCRA.
Nevertheless, because the Alternate Feed Guidance has not yet been revised to reflect
this position recognized by NRC in the Molycorp TER, and because it is not necessary to
rely on the NRC's classification of the Uranium Material as 11 e.(2) byproduct material
(which in fact should be considered determinative of this issue) the remainder of this
memorandum will demonstrate that, even if the Uranium Material were not considered
source material or 11 e.(2) byproduct material, and as such exempt from RCRA, the
Uranium Material would not, in any event, contain any RCRA listed hazardous wastes,
as required under the Alternate Feed Guidance as currently worded.
2.1 Description of Process which Generated the Uranium Material
This yellowcake conversion process included two primary purification steps: digestion
followed by solvent extraction. Digestion occurred by dissolving the uranium in nitric
acid. The resulting slurry was subjected to solvent extraction using tributyl phosphate
diluted with n-hexane. Process conditions were controlled to extract uranium into the
organic phase. The milling impurities remained in the aqueous phase, a dilute nitric acid
mixture termed raffinate.
The aqueous raffinate stream is primarily a solution of nitric acid, metallic salts, and
trace quantities of uranium and radioactive decay products of natural uranium, primarily
Th-230 and Ra-226. The raffinate stream also contained trace quantities of Th-232,
which is often found in natural uranium ores. The aqueous raffinate stream was
combined with spent sodium hydroxide from nitrous oxide scrubber systems and waste
sodium carbonate solutions. The untreated raffinate stream from solvent extraction was
pumped to an impoundment and allowed to cool. Anhydrous ammonia was added to the
raffinate solution to convert the dilute nitric acid to ammonium nitrate. The final treated
raffinate solution was stored in surface impoundments prior to use as an ammonium
nitrate fertilizer.
Generation of Raffinate Sludge
The addition of the anhydrous ammonia also increased the pH of the raffinate solution
causing the metallic salts and trace quantities of uranium, thorium, and radium to
preCipitate and settle out in the impoundments as raffinate sludge.
Per the Radioactive Material Profile record ("RMPR"), the chemical reagents used in the
above processes included:
• nitric acid
• tributyl phosphate
• n-hexane
• anhydrous ammonia
• barium chloride
• spent sodium hydroxide
• waste carbonate solutions
• recovered weak acids
The presence of residuals of some of these compounds and/or their reaction byproducts
would be expected in the Uranium Material, as discussed in the sections below.
The raffinate sludge was transferred by slurry to other storage ponds as necessary. The
raffinate sludge was accumulated and stored in several impoundments on site, including
Clarifier A basins and Pond 4. No other materials were combined with the stored sludge.
The raffinate sludge was eventually consolidated in the Clarifier A basins to support
decommissioning of Pond 4 and dewatering of the raffinate sludge.
Treatment of Raffinate Solution Phase
The treated raffinate solution was decanted to another impoundment for further
treatment with barium chloride to remove trace levels of radium through co-precipitation.
The radium co-precipitate was periodically combined with the raffinate sludge in the
other impoundments.
Preparation and Packaging of De watered Sludge
The raffinate sludge was slurried from Clarifier A basins and processed through a 225
psi filter press to remove entrained water. The dewatered sludge was placed in one-
cUbic-yard polypropylene bags. Approximately 11,000 tons (wet weight basis) or 5,000
tons (dry weight basis) or 11,500 bags are stored on site awaiting final recycling or
disposal. Based on past experience with similar materials, the quantities could be
underestimated. The Mill license amendment therefore contemplates up to
approximately 150 percent of those quantities.
3.0 Basis and Limitations of this Evaluation
The Uranium Material to be processed at the Denison EFRI White Mesa Mill consists
solely of the dewatered raffinate sludge currently stored on site at the Facility.
Physical and chemical properties of the raffinate sludge have been determined at
different times to support site characterization activities and treatability studies. The
results of those determinations were described in several reports prepared subject to the
authority of the State of Oklahoma Department of Environmental Quality and/or the NRC
in the process of site decommissioning including the RCRA Facility Investigation Report
(RFI) and the Site Characterization Report (SCR).
As discussed in Section 2.0, above, the Uranium Material contains greater than 0.05%
source material, and is exempt from RCRA, regardless of its process history or chemical
composition, and no further RCRA analysis is required. Also, the Uranium Material has
been classified as 11e.(2) byproduct material by NRC under 40 CFR 261.4(a)(4).
Because 11 e.(2) byproduct material is exempt from RCRA, for this reason also the
Uranium Material is exempt from RCRA. The following evaluation of characterization
data is provided to demonstrate that even if the Uranium Material were not categorically
exempt from RCRA, it is not and does not contain RCRA listed hazardous waste.
The site and Uranium Material characterizations discussed above and enumerated in the
following table were performed subject to the authority of the State of Oklahoma
Department of Environmental Quality and/or the NRC in the process of site
decommissioning. Characterization of the Uranium Material comprised nine analyzed
samples from the following locations and conditions:
Condition of Sample Name(s) Analyses Number of
Uranium Material Samples
Prior to dewatering Raw Sludge or Metals, 4
Raffinate Sludge or radionuclides,
Pond 4 -1994 ammonia, nitrate,
fluoride
Leachate from Raw Sludge Leachate or Metals, 1 composite of 4
Uranium Material Pond 4 Composite -1994 radionuclides, samples
ammonia, nitrate,
fluoride
Prior to dewatering Raffinate Sludge or VOCs, SVOCs 1
Basin 1 of Clarifier A -
1995
Dewatered Dewatered Sludge -2003 Metals, 1
Uranium Material radionuclides,
ammonia, nitrate,
fluoride
Dewatered Dewatered Sludge -2013 Fluoride, nitrate + 1
Uranium Material nitrite as nitrogen,
ammonia as
nitroQen
Water removed Dewatering Filtrate -2003 Metals, 1
from Uranium radionuclides,
Material ammonia, nitrate,
fluoride
Leachate from Dewatered Sludge Metals, 1
dewatered Leachate -2003 radionuclides,
Uranium Material ammonia, nitrate,
fluoride
The sampling was representative of a continuous process stream under the control of
the generator from a process which did not vary appreciably over time. All analyses
were performed by laboratories possessing State of Oklahoma and/or NELAC
certification for the analyses performed. As a result, these studies provide sufficiently
representative characterization to assess the regulatory status, worker safety
environmental hazards, and chemical and processing properties of the Uranium
Material.
The following RCRA evaluation is based on information from the following sources;
1. SFC RCRA Facility Investigation Report ("RFI", 1997)
2. Current and historic SFC Uranium Material analytical data.
3. Interviews with Sequoyah Fuels personnel in March 2010.
4. Denison EFRI Protocol for Determining Whether Alternate Feeds Are Listed
Hazardous Wastes (Denison, November 1999).
5. RMPR for the SFC Uranium Material (February 2010, revised June 2012).
6. Basis of Hazardous Material and Waste Determinations from the RMPR
(February 2010)
7. Affidavit of John Ellis, SFC President (June 2010).
Denison EFRI has developed a "Protocol for Determining Whether Alternate Feed
Materials are Listed Hazardous Wastes" (November 22, 1999) ("the Protocol"). The
Protocol has been developed in conjunction with, and accepted by, the State of Utah
Department of Environmental Quality ("UDEQ") (Letter of December 7,1999). Copies of
the Protocol and UDEQ letter are provided in Attachment 2 of this Report. The RCRA
evaluation and recommendations in this Report were developed in accordance with the
Protocol.
4.0 Application of Protocol to Uranium Material
4.1 Source Investigation
Several of the information sources enumerated above were used to perform the Source
Investigation indicated in Box 1 of the flow diagram (the "Protocol Diagram") that forms
part of the Protocol.
The following sections describe the status of the Uranium Material relative to RCRA
Characteristic and RCRA Listed Hazardous Waste regulations, and relative to the
specific parameters identified in the QenisonEFRI/UDEQ Hazardous Waste Protocol.
Although alternate feed materials are being recycled to recover uranium and hence are
permitted to contain constituents that may be considered RCRA characteristic wastes in
other circumstances, for completeness, this Report also determines whether or not the
Uranium Material contains any such constituents.
4.2 Detennination Methods in the Denison EFRI I UDEQ Protocol
4.2.1 Regulatory History of the SFC Uranium Material
The NRC issued Source Material License SUB-1 01 0 to Sequoyah Fuels in 1970 for
conversion processing of natural uranium concentrates/yellowcake, which process
resulted in the generation of the Uranium Material. This License was modified by the
NRC from an operational to a reclamation license on September 30, 1990.
In 1993, the U.S. Environmental Protection Agency ("EPA") issued an Administrative
Order on Consent ("AOC") requiring that the Facility should be remediated pursuant to
RCRA. Pursuant to the AOC, SFC prepared a RCRA Facility Investigation Report and
ACRA Corrective Action Plan.
On December 11, 2002, NRC issued Amendment 29 to SFC's Source Material License,
classifying the Uranium Material as 11 e.(2) byproduct material. In a communication to
EPA in 2006, NRC affirmed that:
1. the Site was subject to the regulatory oversight of NRC,
2. the Site therefore was to be decommissioned under 10CFR Part 40, Appendix A,
and
3. NRC would ensure that the contaminants addressed by the AOC would be
properly managed.
NRC's 2002 communication requested that EPA close their AOC. EPA subsequently
terminated the AOC in December 2009.
The Uranium Material, which has materially not changed in form or content since first
being produced in 1970, remains definitional source material as per 40 CFR Part 261.4,
and is explicitly exempt from regulation under RCRA. It has also been classified as
11 e.(2) byproduct material by NRC, and for this reason also is explicitly exempt from
regulation under RCRA. However, for the sake of completeness, Denison EFRI has
required the following evaluation to confirm that even if the Uranium Material were not
exempt from RCRA, it is not and does not contain, what would otherwise be considered
a RCRA-listed waste, or a RCRA characteristic waste.
The Uranium Material has not been classified or treated as listed hazardous waste nor
has it been in contact with any listed hazardous wastes.
~.2.2 Evaluation of Potential RCRA Listings Associated with Specific Contaminants
For potential alternate feeds that are not exempt from RCRA, the Protocol describes
additional steps Denison EFRI will take to assess whether contaminants associated with
any potential RCRA waste listings are present, and the likelihood that they resulted from
RCRA listed hazardous wastes or RCRA listed processes. These steps include
tabulation of all potential listings associated with each known chemical contaminant in
the material, and the review of chemical process and material/waste handling history at
the site to assess whether the known chemical contaminants in the material resulted
from listed or non-listed sources. This evaluation is described in Box 8 and Decision
Diamonds 9 through 11 in the Protocol Diagram.
If the results of the evaluation indicate that the contaminants are not listed waste, the
Protocol specifies an additional assessment of whether the data on which this
determination was made is sufficiently representative, or whether an ongoing
acceptance sampling program should be implemented, and a similar evaluation
performed on any new constituents identified during acceptance sampling.
In the case of the Uranium Material, Steps 9 through 11 are not required as indicated by
the statements provided in the Affidavit of John Ellis. However, for the sake of a
thorough due diligence evaluation, Steps 9 through 11 were completed, and the results
are presented below.
5.0 Chemical Contaminants
Determination of whether the Uranium Material is or contained potential RCRA-listed
waste included consideration of the source history provided in the RMPR .. and through
interviews with Sequoyah Fuels personnel in March 2010, and the analytical data
provided from material sampling analyses presented in the RMPR.
Four samples were collected in March 1994 from Pond 4 for the purpose of determining
concentrations of metals and radionuclides in the raffinate sludge; the averages of
analytical results of these samples are presented in Table 1 of the RMPR as Raw
Sludge. A composite sample was developed from these samples for the purpose of
collecting a leachate; the analytical results of the leachate are presented in Table 1 of
the RMPR as Raw Sludge Leachate.
The raffinate sludge in Pond 4 was transferred to Clarifier A basins between 1993 and
1995. A single sample of raffinate sludge was collected from Basin 1 of Clarifier A in
January 1995 to determine the concentration of volatile and semivolatile organic
compounds; the basis for the selection of constituents was provided as Attachment 01 ci
to the RMPR. The analytical results of this sample exceeding the respective method
detection limits are presented in Table 2 of the RMPR. The results presented in Table 2
are for sludge that had not been subjected to dewatering. The laboratory report of results
for each constituent for this sample is provided as Attachment 01 cii.
Raffinate sludge was collected in May 2003 from Basin 1 of Clarifier A for the purpose of
testing feasibility of dewatering the raffinate sludge using a pressurized plate filter press.
After dewatering by the filter press, three samples were developed and analyzed for
metals and radionuclides. The three samples included the dewatered sludge, the water
expelled from the sludge as a result of dewatering (filtrate), and a leachate derived from
the dewatered sludge. The analytical results of these samples are presented in Table 1
as Dewatered Sludge, Dewatering Filtrate, and Dewatered Sludge Leachate,
respectively. The laboratory reports for these samples are provided as Attachment
01 ciii.
Analyses identified as "Dewatered Sludge" most closely characterize the Uranium
Material, as they were collected from the Uranium Material in the dewatered form in
which the material will be shipped to the Mill. However, constituents identified in the raw
non-dewatered sludge and its leachate may be considered to qualitatively indicate the
potential presence of additional constituents, specifically ammonia, nitrate/nitrite, and
fluoride, in the Dewatered Sludge.
There were no processes conducted at the site which fall under the category of "P' listed
hazardous wastes from non-specific sources as designated in the following seven
categories:
• Spent solvent wastes (F001-F005)
• Wastes from electroplating and other metal finishing operations (F006-F012,
F019)
• Dioxin-bearing wastes (F020-F023 and F026-F028)
• Wastes from the production of certain chlorinated aliphatiC hydrocarbons (F024,
F025)
• Wastes from wood preserving (F032, F034, and F035)
• Petroleum refinery wastewater treatment sludges (F037 and F038)
• Multi-source leachate (F039)
There were no processes conducted at the site which fall under the category of "K" listed
hazardous wastes from specific sources and designated in the following 13 categories:
• Wood preservation (K001)
• Inorganic pigment manufacturing (K002 -K008)
• Organic chemicals manufacturing (K009-K030, K083, K085, K093-K096, K103-
K105, K107-K118, K136, K149-K151, K156-K159, K161, K174-K175, K181)
• Inorganic chemicals manufacturing (K071 , K073, K106, K176-178)
• Pesticides manufacturing (K031-K043, K097 -K099, K123-K126, K131-K132)
• Explosives manufacturing (K044-K047)
• Petroleum refining (K048-52, K170-K172)
• Iron and steel production (K061-K062)
• Primary aluminum production (K088)
• Secondary lead production (K069, K100)
• Veterinary pharmaceuticals manufacturing (K084, K1 01-K1 02)
• Ink formulation (K086)
• Coking (K060, K087, K141-K145, K147-K148)
The Uranium Material does not contain any "P" or "U" listed wastes as it contains no
discarded commercial chemical products, off-specification species, container residues,
and spill residues thereof. Any chemicals used in the conversion process and treatment
process which generated the raffinate sludge/Uranium Material were used for their
intended purpose and are not waste materials.
5.1 Volatile Organic Compounds
The analytical results for the total VOCs in indicated that two ketone compounds, 2-
butanone (also called methyl ethyl ketone) and 2-hexanone, were reported at very low
concentrations in the samples for total analYSis. 2-butanone was reported at 0.3
milligrams per kilogram ("mg/kg"). 2-hexanone was reported at 0.08 mg/kg.
Review of the site operational history, processes and chemicals, indicated that neither of
these compounds were used or present on the Site. Neither of the compounds has
been associated .. directly or indirectly .. with the Facility's processes, nor result from the
breakdown of chemicals which are associated with the process. Both of these ketones
are common laboratory solvents and extractants and multiple laboratory pathways exist
that could introduce them during the sample preparation and analytical processes.
Ketones, including 2 butanone, are present in a number of commonly used supplies in
labs and field sampling programs, including marker pens, label adhesives, and cleaners.
Extensive experience at RCRA, CERCLA, and FUSRAP remediation sites indicates that
ketones, including 2 butanone and 2-hexanone, which are common laboratory solvents
and analytical standards, are consistently present due to laboratory influences or field
sample contamination, and are often not actually site contaminants. The presence of 2-
hexanone may also be an impurity in the n-hexane used in SFC's extraction process.
.J
The detection of these two compounds can be inferred to be present due to laboratory
influences and the compounds are not likely present as constituents of the Uranium
Material.
5.2 Semi-Volatile Organic Compounds
No semi-volatile constituents were detected in the Uranium Material.,
5.3 Other Non-Metal Inorganic Compounds
The sampling results for Ammonia, Nitrate/Nitrite, Fluoride, and Phosphorus indicate
detectable levels of these constituents in the Uranium Material either prior to or after
dewatering.
Dewatered sludge was analyzed for ammonia as nitrogen, nitrate/nitrate as nitrogen and
phosphorus. Fluoride was not analyzed in the dewatered sludge samples but was
analyzed in the raw non-dewatered sludge. The raw sludge result was interpreted to
indicate its potential presence in dewatered Uranium Material.
Evaluation of RCRA listings associated with the analyzed metals is provided in attached
Table 1 and summarized below.
5.3.1 Ammonia as N
Ammonia compounds are not RCRA listed wastes. Ammonia is present in the Uranium
Material as a result of the anhydrous ammonia added to the residuals of the conversion
process to recover dilute nitric acid as ammonium nitrate. No RCRA listings are
applicable to the ammonia present in the Uranium Material.
5.3.2 Nitrate/Nitrite as N
Nitrate may carry RCRA listing U217 if it resulted from the disposal of thallium nitrate as
commercial chemical products, or manufacturing chemical intermediates. There is no
reason that this compound would be present as chemical product, off-spec product, or
manufacturing byproduct on the Site. Nitrate/nitrite compounds are present due to the
use of nitric acid in the uranium digestion process. The U listing is not applicable to the
Uranium Material.
5.3.3 Phosphorus
Phosphorus may carry RCRA listings as follows if it resulted from the disposal of
commercial chemical products, off-spec commercial chemical products, or
manufacturing chemical intermediates containing the compounds specified below:
U087 O,O-diethyl S-methyl dithiophosphate
U 145 lead phosphate
U 189 phosphorous sulfide
U24 zinc phosphide
P006 aluminum phosphide
P040 O,O-diethyl O-pyrazinyl phosphate
P041 Diethyl-p-nitrophenyl phosphate
Ii]
P043 Diisopropylfluorophosphate (DFP)
P08S Octamethyl diphosphoramide
P111 Diphosphoric acid tetraethyl ester (tetraethylpyrophosphate)
P062 Hexaethyl tetraphosphate
P096 Hydrogen phosphide (phosphine)
P039 Phosphorodithioic acid 0,0 diethyl S-[2-(ethylthio)ethyl diethyl] ester
P094 Phosphorodithioic acid 0,0 diethyl S--(ethylthio)ethyl diethyl] ester
P 109 Tetraethyl dithiopyrophosphate
P122 Zinc phosphide
The above compounds result primarily from the synthesis of pesticides, chemical
warfare agents, incendiary weapons, and lead-based fuel additives. None of these
compounds were used or present on the Site. None of these compounds has been
associated~ directly or indirectly~ with Facility processes, nor result from the breakdown
of chemicals which are associated with the process.
Phosphorus may carry RCRA listings K037, K038, K039, or K040 if it resulted from
wastewaters and byproducts form the synthesis of sulfo-or phospho-pesticides. None
of these processes was ever conducted at the Site.
Phosphorus is present as a residual of the tributyl phosphate used in the uranium
hexafluoride extraction step. None of the RCRA listings are applicable to the Uranium
Material.
5.3.4 Fluorides
Fluorides may carry RCRA listings UOOS, U033, U07S, U134, U121, U120, P043, POS6,
POS7, POS8 if they resulted from the disposal of acetamide, carbonic difluoride,
dichlorodifluoromethane, fluoranthene, hydrofluoric acid, trichlorofluoromethane,
diisopropylfluorophosphate (DFP), fluorine, fluoroacetamide, or fluoroacetic acid.
Fluoride is present as a residual from the addition of fluoride to convert uranium oxide
into uranium hexafluoride in the SFC process. None of the above RCRA listings applies
to the fluorides present at the Site.
5.4 Metals
A summary of the RCRA evaluation findings for the metal analytes identified in the
Uranium Material is provided in Table D1 of the RMPR.
All samples listed in Table 1 of the RMPR were analyzed for all the analytes identified
below with one exception. Mercury was not analyzed in the 1994 raw sludge or leachate
samples. Other than this exception, all samples were analyzed for total metals and
results indicate that the metals, aluminum, antimony, arsenic, barium, beryllium,
cadmium, calcium, chromium, cobalt, copper, iron, lead, lithium, magnesium,
manganese, mercury, molybdenum, nickel, potassium, radium, selenium, sodium, silver,
strontium, thallium, vanadium, zinc, and zirconium, were present in the Uranium
Material. Evaluation of RCRA listings associated with the analyzed metals is provided in
attached Table 2 and summarized below.
11
5.4.1 Aluminum
Aluminum wastes may be associated with only one RCRA listing, P006, if they resulted
from disposal of aluminum phosphide commercial chemical products, off-spec
commercial chemical products, or manufacturing chemical intermediates. Aluminum
phosphide is used as an insecticide and fumigant, and in semiconductor manufacturing.
There is no reason this compound would be present as a chemical product, off-spec
product or manufacturing byproduct on the Site. Aluminum is a natural constituent in
some uranium ores and would be present in trace levels in precipitates from the
conversion process at the Site. The P006 listing does not apply to the SFC Uranium
Material.
5.4.2 Antimony
Antimony wastes may carry the following K listings if they resulted from the specific
industries listed here:
K021 fluoromethane production
K161 dithiocarbamate production
K177 antimony oxide speculative accumulation
None of the above operations or processes was ever conducted at the SFC facility.
Antimony is a natural constituent in some uranium ores and would be present in trace
levels in precipitates from the conversion process at the Site. None of the K listings are
applicable to SFC Uranium Material.
5.4.3 Arsenic
Arsenic wastes can carry RCRA listing U136, P011, or P012 if they resulted
(respectively) from the disposal of cacodylic acid, arsenic trioxide, or arsenic pentoxide
commercial chemical products, off-spec commercial chemical products, or
manufacturing chemical intermediates. Cacodylic acid is used as an herbicide for
grasses and tree thinning, as a soil sterilizer, and as a chemical warfare agent. Arsenic
trioxide is used in production of pigments, enamels aniline colors, and decolorizing
glass. It is also used in formulation of insecticides, herbicides, rodenticides, sheep dip
products and wood and hide preservatives. Arsenic pentoxide is used in producing
arsenates, insecticides and weed killers, for dyes, printing and glass coloring, and in
formulation of metal adhesives. There is no reason this any of these compounds would
be present as chemical products, off-spec products or manufacturing byproducts on the
Site.
Arsenic wastes may carry the following F or K listings if they resulted from the specific
industries listed here:
F032, F034, F035
F039
K031
K060
K084, K1 01, K102
K161
K171, K172,
wood treating
leachates from multi-source landfills
cacodylic acid production
coking
veterinary pharmaceuticals
dithiocarbamate production
petroleum refining
K177 antimony or antimony oxide production
None of the above operations or processes was ever conducted at the SFC facility.
Arsenic is a natural constituent in tantalum and tin ores processed at the Site. It is a
natural constituent in some uranium ores and would be present in trace levels in
precipitates from the conversion process at the Site. None of the F or K listings are
applicable to the Uranium Material.
5.4.4 Barium
Barium may be associated with one RCRA listing, P013, if it resulted from the disposal
of barium cyanide commercial chemical products, off-spec commercial chemical
products, or manufacturing chemical intermediates. Barium cyanide is used in metal
finishing and electroplating. There is no reason barium would be present as a chemical
product, off-spec product, or manufacturing byproduct on the Site.
Barium chloride was added to one of the water treatment impoundments to co-
precipitate radium from the decanted raffinate solution and the precipitated barium
sludges were periodically combined with raffinate sludge/Uranium Material in other
impoundments. Residual barium is present as a byproduct of the raffinate solution
treatment and the P013 listing does not apply to the Uranium Material.
5.4.5 Beryllium
Beryllium may be associated with one RCRA listing, P015, if it resulted from the disposal
of commercial chemical beryllium powdered products, off-spec commercial chemical
products, or manufacturing chemical intermediates. Beryllium is present as a
commercial pure product in only a few industrial applications such as nuclear reactor
operations, neutron source generators, solid rocket propellants, and inertial guidance
systems. There is no reason beryllium would be present as a chemical product, off-
spec product or manufacturing byproduct on the Site.
Beryllium is a natural constituent in uranium ores, and concentrates and would be
present in trace levels in precipitates from the conversion process at the Site. The P015
listing does not apply to the Uranium Material.
5.4.6 Cadmium
Cadmium wastes may carry the following F or K listings if they resulted from the specific
industries listed here:
F006 electroplating
F039 leachates from mUlti-source landfills
K061 steel furnaces
K064 copper production
K069 lead smelting
K177 antimony or antimony oxide production
None of the above operations or processes was ever conducted at the Site. Cadmium is
a natural constituent in some uranium ores and would be present in trace levels in
, " ,..;
precipitates from the conversion process at the Site. None of the F or K listings are
applicable to Uranium Material.
5.4.7 Calcium
Calcium wastes can carry RCRA listing U032 or P021 if they resulted (respectively) from
the disposal of calcium chromate or calcium cyanide commercial chemical products, off-
spec commercial chemical products, or manufacturing chemical intermediates. Calcium
chromate is used in the manufacture of pigments, oxidizers, catalysts, medicines,
glazes, colored glass, inks and paints. It is also used in anodizing, engraving, etching,
dyeing and finished metal cleaning. Calcium cyanide is used as a rodenticide/fumigant
for grain and fruit production and storage, in gold leaching operations, and in chemical
synthesis of other cyanides. There is no reason any of these compounds would be
present as chemical products, off-spec products or manufacturing byproducts on the
Site.
It is a natural constituent in some uranium ores and would be present in trace levels in
precipitates from the conversion process at the Site. and therefore the U032 and P021
listings do not apply to the Uranium Material.
5.4.8 Chromium
Chromium wastes can carry RCRA listing U032 if they resulted from the disposal of
chromic acid commercial chemical products, off-spec commercial chemical products, or
manufacturing chemical intermediates. Chromic acid is used in the manufacture of
pigments, oxidizers, catalysts, medicines, glazes, colored glass, inks and paints. It is
also used in anodizing, engraving, etching, dyeing and finished metal cleaning. There is
no reason this compound would be present as chemical product, off-spec product or
manufacturing byproduct on the Site.
Chromium wastes may carry the following F or K listings if they resulted from the specific
industries listed here:
P006
P019
F035
F037, F038
F039
K002, K003
electroplating
aluminum coating
wood treating
petroleum refining
leachates from multi-source landfills
chrome pigment production
None of the above operations or processes was ever conducted at the Facility.
Chromium is a natural constituent in some uranium ores and would be present in trace
levels in precipitates from the conversion process at the Site. None of the F or K listings
are applicable to Uranium Material.
5.4.9 Cobalt
Cobalt is a natural constituent in uranium ores and natural uranium concentrates and
would be present in trace levels in precipitates from the conversion process at the Site.
Cobalt wastes are not listed under RCRA.
5.4.10 Copper
Copper wastes can carry RCRA listing P029 if they resulted from the disposal of cuprous
cyanide or cupric cyanide commercial chemical products, off-spec commercial chemical
products, or manufacturing chemical intermediates. These compounds are used in
electroplating, anti-foulant in paints, insecticides, and as a catalyst for organic synthesis.
There is no reason any of these compounds would be present as chemical products, off-
spec products, or manufacturing byproducts on the Site.
Copper is a natural constituent in some uranium ores and would be present in trace
levels in precipitates from the conversion process at the Site. The P029 listing is not
applicable to the Uranium Material.
5.4.11 Iron
Iron is the world's most common metal element, and is present in nearly all background
soils, rock, and uranium ores and concentrates. Iron wastes are not listed under RCRA.
5.4.12 Lead
Lead wastes can carry RCRA listings U144, U145, U146 or P11 0 if they resulted from the
disposal (respectively) of lead acetate, lead phosphate, lead subacetate, or tetraethyl
lead commercial chemical products, off-spec commercial chemical products, or
manufacturing chemical intermediates. Lead acetate is used in dyeing, pigments,
paints, hair coloring, waterproofing and varnishes. It is also used as a laboratory
reagent and in cyanide gold leaching. Lead phosphate is used as a stabilizing agent in
some plastic resins. Lead subacetate was formerly added to sugar solutions in food
products as a decolorizing agent. Tetraethyllead is synthesized solely as an anti-knock
additive in gasoline. There is no reason any of these compounds would be present as
chemical product, off-spec product, or manufacturing byproduct on the Site.
Lead wastes may carry the following ForK listings if they resulted from the specific
industries listed here:
F035
F039
F037, F038, K048,K049, K051,K052
K002,K003,K005
K046
K061, K062
K064
K069, K100
K086
wood treating
leachates from multi-source landfills
petroleum refining
chrome pigment production
explosive initiator production
iron and steel furnaces
copper production
lead smelting
ink formulation
None of the above operations or processes was ever conducted at the Site. It is a
natural constituent in some uranium ores and would be present in trace levels in
precipitates from the conversion process at the Site. None of the F or K listings are
applicable to Uranium Material.
.I ;
5.4.13 Lithium
Lithium is a natural constituent in uranium ores and natural uranium concentrates. It is a
natural constituent in some uranium ores and would be present in trace levels in
precipitates from the conversion process at the Site. Lithium wastes are not listed under
RCRA.
5.4.14 Magnesium
Magnesium is a natural constituent in uranium ores and natural uranium concentrates. It
is a natural constituent in some uranium ores and would be present in trace levels in
precipitates from the conversion process at the Site. Magnesium wastes are not listed
under RCRA.
5.4.15 Manganese
Manganese may be associated with one RCRA listing, P196, if it resulted from the
disposal of manganese dimethyldithiocarbamate commercial chemical products, off-spec
commercial chemical products, or manufacturing chemical intermediates. Manganese
dimethyldithiocarbaniate is used almost solely as a pesticide. There is no reason
manganese dimethyldithiocarbaniate would be present as chemical product, off-spec
product, or manufacturing byproduct on the Site.
It is a natural constituent in some uranium ores and would be present in trace levels in
precipitates from the conversion process at the Site. The P196 listing does not apply to
the Uranium Material.
5.4.16 Mercury
Mercury wastes can carry RCRA listings U151, P065 or P092 if they resulted from the
disposal (respectively) of mercury metal, mercury fulminate, or phenyl mercuric acetate
commercial chemical products, off-spec commercial chemical products, or
manufacturing chemical intermediates. Mercury metal product has been used in
electrolytiC cells, arc lamps, dental amalgams, mirror coatings. It was formerly used in
nuclear power reactors and as a boiler fluid, and continues to be used in measurement
instruments and as a reaction catalyst. Mercury fulminate is used primarily as an
explosive initiator in military explosives, and is too unstable for most other applications.
Phenyl mercuric acetate is a microbicide used as a fungicide, spermicide, and anti-
mildew agent. There is no reason any of these compounds would be present as
chemical product, off-spec product or manufacturing byproduct on the Site.
Mercury wastes may carry K listings K071 or K106 if they resulted from chlorine cell
cathode liquid disposal. No chlorine processing was ever conducted at the Facility. It is
a natural constituent in some uranium ores and would be present in trace levels in
precipitates from the conversion process at the Site. None of the K listings are
applicable to the Uranium Material.
5.4.17 Molybdenum
Molybdenum is a natural constituent in uranium ores and natural uranium concentrates
and would be present in trace levels in precipitates from the conversion process at the
Site. Molybdenum wastes are not listed under RCRA.
5.4.18 Nickel
Nickel wastes can carry RCRA listings P073 or P074 if they resulted from the disposal
(respectively) of nickel carbonyl or nickel cyanide commercial chemical products, off-
spec commercial chemical products, or manufacturing chemical intermediates. Nickel
carbonyl and nickel cyanide are both used in electroplating of nickel coatings. Nickel
carbonyl is also used as a chemical reagent. There is no reason any of these
compounds would be present as chemical product, off-spec product, or manufacturing
byproduct on the Site.
Nickel wastes may carry RCRA listing F006 if they resulted from disposal of
electroplating sludge. No electroplating was ever conducted at the Site. Nickel is a
natural constituent in some uranium ores and would be present in trace levels in
precipitates from the conversion process at the Site. The F006 listing is not applicable to
Uranium Material.
5.4.19 Potassium
Potassium wastes can carry RCRA listings P098 or P099 if they resulted from the
disposal (respectively) of potassium cyanide or potassium silver cyanide commercial
chemical products, off-spec commercial chemical products, or manufacturing chemical
intermediates. Potassium cyanide is used in gold and silver ore processing,
electroplating, and as an analytical reagent and insecticide. Potassium silver cyanide is
used as an antiseptic and in silver plating. There is no reason either of these
compounds would be present as chemical product, off-spec product or manufacturing
byproduct on the Site.
Potassium wastes may carry RCRA listing K161 if they resulted from dithiocarbamate
production. No organic synthesis was ever conducted at the SFC facility. Potassium is
a natural constituent in some uranium ores and would be present in trace levels in
precipitates from the conversion process at the Site. The K161 listing is not applicable to
the Uranium Material.
5.4.20 Radium
Radium is a natural constituent in uranium ores and natural uranium concentrates a and
would be present in trace levels in precipitates from the conversion process at the Site.
Radium wastes are not listed under RCRA.
5.4.21 Selenium
Selenium wastes can carry RCRA listings U204, U205, P103, or P114 if they resulted
from the disposal (respectively) of selenious acid, selenium disulfide, selenourea, or
thallium selenide commercial chemical products, off-spec commercial chemical
products, or manufacturing chemical intermediates. Selenious acid and thallium
'1
selenide are used for cold blackening and decorative finishes of metals. Selenium
disulfide is used in medical preparations. Selenourea is methylated to make protective
glass coatings. There is no reason either of these compounds would be present as
chemical products, off-spec products, or manufacturing byproducts on the Site.
Selenium is a natural constituent in some uranium ores and would be present in trace
levels in precipitates from the conversion process at the Site, and the U and P listings
are not applicable to Uranium Material.
5.4.22 Silver
Silver may be associated with RCRA listings P099 and P104 if it resulted from the disposal of silver
potassium cyanide or silver cyanide as commercial chemical products, off-spec commercial
chemical products, or manufacturing chemical intermediates. There is no reason any of
these compounds would be present as chemical product, off-spec product or
manufacturing byproduct on the Site.
Silver is a natural constituent in some uranium ores and concentrates and would be
present in trace levels in precipitates from the conversion process at the Site, and the U
and P listings are not applicable to Uranium Material.
5.4.23 Sodium
Sodium wastes can carry RCRA listing U236 if they resulted from the disposal of
dimethyl biphenyl diyl bis(azo)bis amino hydroxyl tetrasodium salt commercial chemical
products, off-spec commercial chemical products, or manufacturing chemical
intermediates, which are used in research chemistry and biochemistry. They may also
carry RCRA listings POS8, P10S or P106 if they resulted from the disposal (respectively)
of sodium fluoroacetic acid sodium salt, sodium azide, or sodium cyanide commercial
chemical products, off-spec commercial chemical products, or manufacturing chemical
intermediates. Fluoroacetic acid sodium salt is used primarily as a rodenticide. Sodium
azide is used in diagnostic medicine, and as an explosive in air bag inflators. Sodium
cyanide is used in manufacture of dyes, pigments, nylon, insecticides, and chelating
compounds. It is also used in gold and silver extraction, metal treating and cleaning and
ore flotation. There is no reason any of these compounds would be present as chemical
product, off-spec product or manufacturing byproduct on the Site.
Sodium wastes may carry the RCRA listing K161 if they resulted from dithiocarbamate
production. No organic synthesis was ever conducted at the Facility. Sodium is present
as a residual of spent sodium hydroxide added to the process during pH adjustment
generation of the Uranium Material and remains in precipitates from the conversion
process at the Site. The K161 listing is not applicable to SFC Uranium Material.
5.4.24 Strontium
Strontium is the 14th most common element in the earth's crust and can be expected to
be a natural constituent in some uranium ores and a trace constituent in some natural
uranium concentrates. It can be expected to be present in trace levels in precipitates
from the conversion process at the Site. Strontium wastes are not listed under RCRA.
) "
5.4.25 Thallium
Thallium wastes can carry the following RCRA listings if they resulted from the disposal
of commercial chemical products, off-spec commercial chemical products, or
manufacturing chemical intermediates listed below.
U214 thallium (I) acetate
U215 thallium (I) carbonate
U216 thallium chloride
U217 thallium (I) nitrate
P114 selenious acid dithallium salt
P115 sulfuric acid dithallium salt
Thallium carbonate is used as an analytical standard, and in production of synthetic
diamonds. Thallium chloride is used as a chlorination catalyst and as a sun lamp
radiation monitor. Thallium nitrate is used to produce green-fire pyrotechnics and as an
analytical laboratory standard. Selenious acid and its salts are used for blackening and
decorative finishing of product metals. Sulfuric acid dithallium salt is used in ant-killer
mixtures. There is no reason any of these compounds would be present as chemical
product, off-spec product or manufacturing byproduct on the SFC site. Thallium acetate
is used in ore flotation but was not used at the Facility.
Thallium wastes may carry RCRA listing K178 if they resulted from the manufacture of
ferric chloride as a byproduct from titanium dioxide production. No ferric chloride
processing was ever conducted at the Facility. It is a natural constituent in some
uranium ores and would be present in trace levels in precipitates from the conversion
process at the Site. The K178 listing is not applicable to the Uranium Material.
5.4.26 Vanadium
Vanadium wastes can carry RCRA listing P120 if they resulted from the disposal of
vanadium pentoxide (black flake) commercial chemical products, off-spec commercial
chemical products, or manufacturing chemical intermediates. There is no reason
vanadium compounds would be present as chemical products, off-spec products, or
manufacturing byproducts on the Site.
Vanadium is a constituent of natural ores and concentrates and would be present in
trace levels in precipitates from the conversion process at the Site. The K178 listing is
not applicable to the Uranium Material.
5.4.27 Zinc
Zinc wastes can carry RCRA listings U249, P121, P122, or P205 if they resulted from
the disposal (respectively) of low concentration zinc phosphide, zinc cyanide, high
concentration zinc phosphide, or zinc dimethyl dithiocarbamate ("Ziram") commercial
chemical products, off-spec commercial chemical products, or manufacturing chemical
intermediates. Zinc phosphides and Ziram are used solely as rodenticides. Zinc
cyanide is used in metal plating, as an insecticide and as a chemical reagent. There is
no reason any of these compounds would be present as chemical product, off-spec
product, or manufacturing byproduct on the Site.
Zinc wastes may carry the RCRA listing K161 if they resulted from Ziram rodenticide
production. No pesticide synthesis was ever conducted at the Facility. Zinc is a natural
constituent in soils, plant and animal tissue, and many natural ores including uranium
ores and concentrates, and would be present in trace levels in precipitates from the
conversion process at the Site. The K161 listing is not applicable to SFC Uranium
Material.
5.5 Summary of RCRA Listed Waste Findings
Based on the information presented above, none of the constituents in the Uranium
Material would be indicative of RCRA listed hazardous waste, even if the Uranium
Material were not already exempt from RCRA as source material and 11e.(2) byproduct
material.
6.0 RCRA Characteristics
The Uranium Material is a near-neutral byproduct of dewatering precipitated aqueous
sludges. As a result it would not be ignitable, corrosive, or reactive per the RCRA
definitions of these characteristics. One Uranium Material sample collected during -1004
and one sollected during 20032012 'Nero was analyzed for RCRA TCLP metals
constituents. No analyzed contaminant exceeded its respective TCLP threshold for
RCRA toxicity characteristic as defined in Table 1 of 40 CFR Part 261.24(b).
Therefore, the test results indicate that that the Uranium Material does not have the
RCRA characteristic of toxicity. The Affidavit from John Ellis of SFC affirms that the
Uranium Material has never been classified for shipment or off-site management as a
RCRA characteristic waste. This is consistent with the source of the constituents and
the treatment process used to develop the Uranium Material.
As discussed in the introduction to this report, the Uranium Material is exempt from
regulation under RCRA; however, even if it were classified as a characteristic hazardous
waste, alternate feed materials are permitted to contain RCRA characteristic wastes
under NRC's Alternate Feed Guidance (10 CFR 40, Appendix A).
Based on all of the above information, the Uranium Material is not a RCRA characteristic
hazardous waste.
7.0 Conclusions and Recommendations
In summary, the following conclusions can be drawn from the RCRA analysis of the Site
information presented above:
1. The Uranium Material is not a RCRA listed hazardous waste because it has been
classified by NRC as 11 e.(2) byproduct material and is therefore exempt from
regulation under RCRA.
2. Even if the Uranium Material had not been classified as 11 e.(2) byproduct
material, the Uranium Material would not be a RCRA listed hazardous waste
because it is an ore that has a natural uranium content of greater than 0.05
weight percent, is therefore source material and, as a result, is exempt from
regulation under RCRA.
. J
3. Even if the Uranium Material were not 11 e.(2) byproduct material or source
material, it would not be a RCRA listed hazardous waste for the following
additional reasons:
a) It was generated from a known process under the control of the generator,
who has provided the Affidavit declaring that the Uranium Material is not and
does not contain RCRA listed hazardous waste. This determination is
consistent with Boxes I and 2 and Decision Diamonds 1 and 2 in the
GeAi59HEFRI/UDEQ Protocol Diagram;
b) The volatile organic compounds detected at very low concentrations in the
Uranium Material can attributed to laboratory contamination and are likely not
actual contaminants in the Uranium Material. None of the processes or
materials associated with any of the RCRA listings for VOCs or SVOC
compounds were ever conducted at the site and none of the listings are
applicable. This determination is consistent with Box 8 and Decision
Diamonds 9 through 11 in the QeffiseREFR I/UDEQ Protocol Diagram;
c) None of the metals in the Uranium Material samples came from RCRA listed
hazardous waste sources. This determination is consistent with Box 8 and
Decision Diamonds 9 through 11 in the DenisonEFRl/UDEQ Protocol
Diagram.
4. The Uranium Material does not exhibit any of the RCRA characteristics of
ignitability, corrosivity, reactivity, or toxicity for any constituent.
8.0
•
•
•
•
•
•
•
References
Austin, G.T. Shreve's Chemical Process Industries, Fifth Edition. McGraw Hill.
New York 1984.
Title 10 Code of Federal Regulations; Chapter I -Nuclear Regulatory
Commission, Part 40 -Domestic Licensing of Source Material: 40.4 -Definitions
(10 CFR 40.4)
Title 10 Code of Federal Regulations; Appendix A -Nuclear Regulatory
Commission, Part 40 -Domestic Licensing of Source Material: Criteria Relating
to the Operation of Uranium Mills and the Disposition of Tailings or Wastes
Produced by the Extraction or Concentration of Source Material From Ores
Processed Primarily for Their Source Material Content (10 CFR 40 Appendix A)
Title 40 Code of Federal Regulations; Protection of the Environment, Part 261 -
Identification and Listing of Hazardous Waste: Subpart A, 261.4 -Exclusions:
Subpart B -Criteria for Identifying the Characteristics of Hazardous Waste and
for Listing Hazardous Waste.
Notzl, H. Sequoyah Fuels Dewatered Tails Process Evaluation for Uranium
Recovery. October 8, 2004
US EPA Chemical Fact Sheets -accessed at www.epa.q ov/chemfact on 10/6/10
Sax, N. Irvin~ and Lewis, Richard L. Sr. Hawley's Condensed Chemical
Dictionary, 11t Edition. Van Nostrand Reinhold. New York 1987.
AMMONIA
Commercial Commercial Non-Specific
Chemicals Chemicals Sources
Acutely Toxic Acutely Hazardous FList
UList PList
NONE
NONE
NONE
- ---
FLUORIDE
Commercial Commercial Non-Specific
Chemicals Chemicals Sources
Acutely Toxic Acutely Hazardous FList
UList PList
U033
Carbonic difluoride,
Carbon oxyfluoride,
Carbonyl fluoride
U075
Dichlorodifluoro
methane
U134
Hydrogen fluoride
P043
Diisoproplyfluorophosp
hate
P056
Fluorine
P057
2-fluoroacetamide
P058
F1uoroacetic acid
sodium salt
NONE
TABLE 1 (Rev. 0): SUMMARY OF POTENTIAL RCRA LISTINGS
IN 40 CFR 261 and APPENDIX VII
ASSOCIATED WITH NON-METALS IN SFC DEWATERED SLUDGE
Specific Industrial Uses and Sources of U or P Is This Listing Applicable to
Sources Listed Element or Compound SFC Sludge?
KList
I
No U [jslinl!s
No P listingS
No F Listings
NONE No K Listings ---
Specific Industrial Uses and Sources of U or P Is This Listing Applicable to
Sources Listed Element or Compound SFC Sludge?
KList
Used in organic synthesis for addition of No. There would be no reason for this compound to be
carbon groups to other structures. present as pure product, byproduct, or off-spec product on
site.
Used as refrigerant in air conditioners, No. There would be no reason for this compound to be
and direct contact freezing. Used in present as pure product, byproduct, or off-spec product on
plastics manufacture, and as solvent and site.
blowing agent.
Catalyst in refinery alkylation, No. fluoride is present as a residual from the conversion of
isomerization, condensation, yellowcake to uranium hexafluoride in the SFC process.
dehydration, and polymerization Hydrogen fluoride present in the sludge is a result of process
processes. Used for organic and use, not disposal. of the product.
inorganic flourination reactions,
production of fluorine gas and aluminum
fluoride, some uranium leaching
processes, and as additive to solid rocket
propellant.
Insecticide No. There would be no reason for this' compound to be
present as pure product, byproduct, or off-spec product on
site.
Production of metallic fluorides and No. There would be no reason for this compound to be
fluorocarbons, fluoridation compounds present as pure product, byproduct, or off-spec product on
for toothpaste and water treatment. site.
Primarily as a rodenticide. I No. There would be no reason for this compound to be
p,resent as pure product, byproduct, or off-spec product on
sIte.
Primarily as a rodenticide. No. There would be no reason for this compound to be
present as pure product, byproduct, or off-spec product on
site.
No F Listings
NONE No K Listings ---
Page 1
INORGANIC NITRA TES2
Commercial Chemicals Commercial Chemicals
Acutely Toxic Acutely Hazardous
UList PList
INGNEU~17
NONE
---
PHOSPHORUS
Commercial Chemicals Commercial Chemicals
Acutely Toxic Acutely Hazardous
UList PList
U087
O,O-diethyl S-methyl
dithiophosphate
U145
Lead phosphate
U189
Phosphorus sulfide,
Phosphorus trisulfide
U249
Zinc phosphide
POO6
Aluminum phosphide
P039
Phosphorodithioic acid
0,0 diethyl S-[2-
e(thylthio) ethyl diethyl]
ester (malathion)
P040
O,O-diethyl O-pyrazinyl
phosphate
P041
Diethyl-p-nitrophenyl
phosphate (parathion)
P043
Diisopropylfluorophosp
hate (DFP)
P062
Hexaethvl - -
TABLE 1 (Rev. 0): SUMMARY OF POTENTIAL RCRA LISTINGS
IN 40 CFR 261 and APPENDIX VII
ASSOCIATED WITH NON-METALS IN SFC DEWATERED SLUDGE
Non-Specific Specific Industrial Uses and Sources of U or P Listed Element Is This Listing Applicable to
Sources Sources or Compound SFC Sludge?
FList KList
:-:!l TI!!<lllO "!JIll!.! t·;! lJ11 t!l~II!l f.u Illio; ';jlnIRQuntlll! I>t-ili!i~~!l1 ;I~ !"ur.:
t!lt!!luct. ~\'r\J\'tllJ~~ nr nlHr-":1'ruihICI 011 sile. ~11!le
I No P Listings
NONE I No F Listings
I NONE -No K Listings
Non-Specific Specific Industrial Uses and Sources of U or P Listed Element Is This Listing Applicable to
Sources Sources or Compound SFC Sludge?
FList KList
Synthesis of pesticides, chemical warfare agents. No. There would be no reason for this compound to be present as pure
product, byproduct, or off-spec product on site.
Used as a stabilizing agent additive in plastic formulation_ No, There would be no reason for this compound to be present as pure
product, bVproduct, or off-spec product on site.
Synthesis of pesticides, chemical warfare agents. No. There would be no reason for this compound to be present as pure
product, byproduct, or off-spec product on site.
Synthesis of pesticides, chemical warfare agents, used as No. There would be no reason for this compound to be present as pure
rodenticide. product, byproduct, or off-spec product on site.
Synthesis of pesticides, chemical warfare agents, No. There would be no reason for this compound to be present as pure
insecticide, fumigant, semiconductor technology. product, byproduct, or off-spec product on site.
Fruit fly insecticide. No. There would be no reason for this compound to be present as pure
product, byproduct, or off-spec product on site.
Synthesis of thionazin insecticide, fungicide, namtatocide. No. There would be no reason for this compound to be present as pure
chemical warfare agents. product. byproduct, or off-spec product on site.
Synthesis of pesticides, chemical warfare agents. No. There would be no reason for this compound to be present as pure
Insecticide and acaicide. product, byproduct, or off-spec product on site.
Synthesis of pesticides, chemical warfare agents. No. There would be no reason for this compound to be present as pure
product, byproduct, or off-spec product on site.
Synthesis of pesticides, chemical warfare agents; contact No. There would be no reason for this compound to be present as pure
insecticide ~roduct, byproduct, or off-spec product on site.
Page 2
tetraphosphate (HETP)
P085
Octamethy
diphosphoramide
(schradan)
P096
Hydrogen phosphide
(phosphine)
P094
Phosphorodithioic acid
0,0 diethyl S-
etheylthio) ethyl diethyl]
ester
PlO9
Tetraethyl
dithiopyrphosphate
(TEDP or sulfotepp)
Plli
Diphosphoric acid
tetraethyl ester
PI22
Zinc phosphide
TABLE 1 (Rev. 0): SUMMARY OF POTENTIAL RCRA LISTINGS
IN 40 CFR 261 and APPENDIX VII
ASSOCIATED WITH NON-METALS IN SFC DEWATERED SLUDGE
Synthesis of pesticides, chemical warfare agents. No. There would be no reason for this compound to be present as pure
Systemic insecticide toxic to plant-chewing insects. product, byproduct, or off-spec product on site.
Organic chemical synthesis, doping agent for No. There would be no reason for this compound to be present as pure
semiconductors, polymerization initiator, condensation product, byproduct, or off-spec product on site.
polymerization cata!y!'t.
Synthesis of pesticides, chemical warfare agents, thion No. There would be no reason for this compound to be present as pure
pesticides. product, byproduct, or off-spec product on site.
Insecticides, chemical warfare agents. No. There would be no reason for this compound to be present as pure
product, byproduct, or off-spec product on site.
Synthesis of pesticides, chemical warfare agents, No. There would be no reason for this compound to be present as pure
incendiary weapons, stabilizer for organic peroxides. product, byproduct, or off-spec product on site.
Synthesis of pesticides, chemical warfare agents, used as No. There would be no reason for this compound to be present as pure
rodenticide. product, byproduct, or off-spec product on site.
NONE No F Listings
K037 Wastewater treatment sludges from the production of No. SFC material is not from this industry. Also it is present primarily
disulfoton. as an accessory metal in uranium ores and concentrates, which are not
listed waste sources.
K038 Wastewater from the wsshing and stripping of phorate No. SFC material is not from this industry. Also it is present primarily
as an accessory metal in uranium ores and concentrates, which are not
listed waste sources.
K039 Filter cake from the filtration of diethylphosphorodithioic No. SFC material is not from this industry. Also it is present primarily
acid in the production of phorate as an accessory metal in uranium ores and concentrates, which are not
listed waste sources.
K040 Wastewater treatment sludges from the production of No. SFC material is not from this industry. Also it is present primarily
phorate as an accessory metal in uranium ores and concentrates, which are not
listed waste sources. -
Page 3
ALUMINUM
Commercial Commercial Non-Specific
Chemicals Chemicals Sources
Acutely Toxic Acutely FList
UList Hazardous
PList
NONE
P006
Aluminum
phosphide
NONE
-
ANTIMONY
Commercial Commercial Non-Specific
Chemicals Chemicals Sources
Acutely Toxic Acutely FList
U List Hazardous
PList
NONE
NONE
NONE
TABLE 2 (Rev. 0): SUMMARY OF POTENTIAL RCRA LISTINGS
IN 40 CFR 261 and APPENDIX VII
ASSOCIATED WITH METALS IN SFC DEWATERED SLUDGE
Specific Industrial Uses and Sources of U or P
Sources Listed Element or Compound
KList
~
Insecticide, fumigant, semiconductor
manufacturing.
-
NONE --
Specific Industrial Uses and Sources of U or P
Sources Listed Element or Compound
KList
.
--
--
--
K021
Spent catalyst from
fluoromethane production
Kl61
Purification solids, baghouse dust
and floor sweepings from
dithiocarbamate acidsJJroduction
KI77
Slag from production or
speculative accumulation of
antimony or antimony oxides
Page 1
Is This Listing Applicable to
SFC Sludge'?
No U Listings
No. There would be no reason for this compound to be
present as pure product, byproduct, or off-spec product
on site.
No F Listings
No K Listings
Is ThisListing Applicable to
SFC Sludge?
No U Listings
No P Listings
No F Listings
No. SFC material is not from this industry. Also,
I antimony is present primarily as an accessory metal in
the tungsten ores, which is not a listed waste source.
No. SFC material is not from this industry. Also,
antimony is present primarily as an accessory metal in
the tungsten ores, which is not a listed waste source.
No. SFC material is not from this industry. Also,
antimony is present primarily as an accessory metal in
the tungsten ores, which is not a listed waste source.
ARSENIC
Commercial Commercial
Chemicals Chemicals
Acutely Toxic Acutely
UList Hazardous
PList
U136
Dimethyl arsenic
acid
(cacodylic acid)
POll
Arsenic trioxide
POl2
Arsenic
Pentoxide
TABLE 2 (Rev. 0): SUMMARY OF POTENTIAL RCRA LISTINGS
IN 40 CFR 261 and APPENDIX VII
ASSOCIATED WITH METALS IN SFC DEWATERED SLUDGE
Non-Specific Specific Industrial Uses and Sources of U or P
Sources Sources Listed Element or Compound
FList KList
Used as herbicide for Johnson grass on
cotton, in timber thinning, as a soil
sterilizing agent, and as a chemical
warfare agent.
Used in production of pigments, aniline
colors, ceramic enamels, and decolorizing
glass, insecticides, herbicides,
rodenticides, wood and hide preservati ves,
and sheep dip.
Used in production of aresenates,
insecticides, dyeing and printing, weed
killers, and colorization of glass. Also
used in metal adhesives.
F032
Wastewater from wood
preserving processes using
creosote and pentachlorophenol
F034
Wastewater from wood
preserving processes using
creosote and pentachlorophenol
F035
Wastewaters from wood
preserving processes using
inorganic preservati ves
F039 --
Leachates from land disposal of
wastes F20 to F22 and F26 to F28
K02l -
Spent catalyst from
fluoromethane production
K03l -
Byproduct salts from MSMA and
cacodylic acid production
K060 -
Ammonia still lime sludge from
coking
K084 -
Wastewater sludge from
veterinary pharmaceutical
production
KIOI -
Distillation tar residues from
veterinary pharmaceutical
production
Page 2
Is This Listing Applicable to
SFC Sludge?
No. There would be no reason for this compound to be
present as pure product, byproduct, or off-spec product
on site.
No. There would be no reason for this compound to be
present as pure product, byproduct, or off-spec product
on site.
No. There would be no reason for this compound to be
present as pure product, byproduct, or off-spec product
on site.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and ~()m .. erllmtt::S. which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also
arsenic is present primarily as an accessory metal in the
uranium ores and concentrates, which are not listed
waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
BARIUM
Commercial Commercial Non-Specific
Chemicals Chemicals Sources
Acutely Toxic Acutely FList
UList Hazardous
PList
NONE
POl3
Barium Cyanide
NONE
BERYLLIUM
Commercial Commercial Non-Specific
Chemicals Chemicals Sources
Acutely Toxic Acutely FList
UList Hazardous
PList
NONE
Beryllium --POlS
Beryllium powder
NONE
TABLE 2 (Rev. 0): SUMMARY OF POTENTIAL RCRA LISTINGS
IN 40 CFR 261 and APPENDIX VII
ASSOCIATED WITH METALS IN SFC DEWATERED SLUDGE
K102 --
Residue from decolorization of
veterinary pharmaceuticals
K161 --
Purification solids, baghouse dust
and floor sweepings from
dithiocarbamate acids production
K 171 Spent hydrotreating catalyst -
from petroleum refining
KIn -
Spent hydrorefining catalyst from
petroleum refining
KIn -
Slag from production or
speculative accumulation of
antimony or antimony oxides
Specific Industrial Uses and Sources of U or P
Sources Listed Element or Compound
KList
--
Used in metallurgy and electroplating.
-
NONE -
Specific Industrial Uses and Sources of U or P
Sources Listed Element or Compound
KList
-
Beryllium powder is used in the aerospace
industry. as a neutron reflector in nuclear
reactor shielding. solid rocket fuel, and in
X-ray tubes. Also used in alloys and parts
in gyroscopes, guidance system
components, instrumentation and controls
such as solenoids. relays, and switches.
--
NONE --
Page 3
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates. which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates. which are not listed waste sources.
Is This Listing Applicable to
SFC Sludge?
No U Listings
No. There would be no reason for this compound to be
present as pure product. byproduct. or off-spec product
on site. Barium resulted from addition of barium
chloride for radium removal in the SFC sludge.
No F Listings
No K Listings
Is This Listing Applicable to
SFC Sludge?
No U Listings
There would be no reason for powdered beryllium to be
present as pure product. byproduct or off-spec product at
SFC.
No F Listings
No K Listings
COPPER
Commercial Commercial
Chemicals Chemicals
Acutely Toxic Acutely
UList Hazardous
PList
NONE
P029
Cuprous or
Cupric Cyanide
CADMIUM
Commercial Commercial
Chemicals Chemicals
Acutely Toxic Acutely
UList Hazardous
PList
NONE
NONE
Non-Specific
Sources
FList
NONE
Non-Specific
Sources
FList
FOO6
Wastewater sludge from
electroplating
F039
TABLE 2 (Rev. 0): SUMMARY OF POTENTIAL RCRA LISTINGS
IN 40 CFR 261 and APPENDIX VII
ASSOCIATED WITH METALS IN SFC DEWATERED SLUDGE
Specific Industrial Uses and Sources of U or P
Sources Listed Element or Compound
KList
--
Used in metallurgy and electroplating,
insecticides, anti-foulants in paints,
catalysts in organic synthesis ..
-
NONE ---
Specific Industrial Uses and Sources of U or P
Sources Listed Element or Compound
KList
--
--
-
-Leachates from land disposal of
wastes F20 to F22 and F26 to F28
K061 -
Steel electric furnace emission
control dust/sludge
K064 --
Acid plant blowdown thickener
slurry/sludge from primary copper
production blowdown
K069 -
Emission control dust/sludge from
secondary lead smelting
KI77
Slag from production or
speCUlative accumulation of
antimony or antimony oxides
Page 4
Is This Listing Applicable to
SFC Sludge?
No U Listinl!;s
No. There would be no reason for this compound to be
present as pure product, byproduct, or off-spec product
on site. Copper is present primarily as an accessory
metal in urani urn ores and concentrates, which are not
listed waste sources.
No F Listings
No K Listings
Is This Listing Applicable to
I
SFC Sludge?
No U Listings
:
No P Listings
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present plimarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates. which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
CALCIUM
Commercial Commercial
Chemicals Chemicals
Acutely Toxic Acutely
UList Hazardous
P List
U032
Calcium chromate
P021
Calcium cyanide
CHROMIUM
Commercial Commercial
Chemicals Chemicals
Acutely Toxic Acutely
UList Hazardous
PList
U032
Chromic acid or
calcium salt of
chromic acid
NONE
TABLE 2 (Rev. 0): SUMMARY OF POTENTIAL RCRA LISTINGS
IN 40 CFR 261 and APPENDIX VII
ASSOCIATED WITH METALS IN SFC DEWATERED SLUDGE
Non-Specific Specific Industrial Uses and Sources of U or P
Sources Sources Listed Element or Compound
FList KList
Used as a pigment, corrosion inhibitor,
oxidizing agent, battery depolarizer, coatin
g for light metal alloys.
Rodenticide, fumigant for greenhouses,
flour mills, grain, seed, and citrus trees,
gold leaching, and synthesis of other
cyanides.
NONE -
NONE ~
Non-Specific Specific Industrial Uses and Sources of U or P
Sources Sources Listed Element or Compound
FList KList
Used in manufacture of pigments,
oxidizers, catalysts, medicines, ceramic
glazes, colored glass, inks, paints, plating,
anodizing, engraving, plastic etching, and
textile dyeing, and metal cleaning.
FOO6 -
Wastewater treatment sludge from
electroplating
FO 19 Wastewater treatment -
sludge from chemical coating of
aluminum
F035 -
Wood treating wastewater
F037 -Refinery oil/water separator solids
F038 -
Refinery secondary oil/water
separator solids
F039 -
Leachates from land disposal of
wastes F20 to F22 and F26 to F28
-
Page 5
Is This Listing Applicable to
SFC Sludge'!
No. There would be no reason for this compound to be
present as pure product, byproduct, or off-spec product
on site.
No. There would be no reason for this compound to be
present as pure product, byproduct, or off-spec product
on site.
No F Listinl'!:s.
No K Listings.
Is This Listing Applicable to
SFC Sludge?
No. There would be no reason for this compound to be
present as pure product, byproduct, or off-spec product
on site.
No P Listings
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is I
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
TABLE 2 (Rev. 0): SUMMARY OF POTENTIAL RCRA LISTINGS
IN 40 CFR 261 and APPENDIX VII
ASSOCIATED WITH METALS IN SFC DEWATERED SLUDGE
KOO2 ---
Wastewater treatment sludge from
production of chrome yellow
pigment
K003 --
Wastewater treatment sludge from
production of chrome molybdate
orange pigment
KOO4 --
Wastewater treatment sludge from
production of zinc yellow pigment
KOOS ---
Wastewater treatment sludge from
production of chrome green
pigment
KOO6 --
Wastewater treatment sludge from
production of chrome oxide green
pigments
KOO7 --
Wastewater treatment sludge from
production of iron blue pigments.
KOO8 --
Oven residue from production of
chrome oxide green pigments
K048 ---
Petroleum refining dissolved air
flotation ("DAF') solids
K049 --
Petroleum refining slop oil
emulsion solids
KOSO --
Heat exchanger bundle cleaning
sludge form petroleum refining
KOSI ---
Petroleum refining API separator
solids
K06l --
Steel electric furnace emission
control dust/sludge
K062 --
Iron and steel manufacturing
pickle liquor
K069 -
Emission control dust/sludge from
secondary lead smeltin"
K086 --
Solvent, caustic and water wash
sludges from ink formulation
Page 6
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from ll)iS induslry. Also it is
present primarily as an accessory metal in uranium ores
and conCcIll~!CS, which lin: not lis't .. :d waste sources ..
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
nnd COncemr(lles. which are not listed waste sources ..
""No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and C(1ncenmllCS, which are not listed waste sources.
No. SFC material is not from IhiS industry. Also it is
present primarily as an accessory metal in uranium ores
and CQIl~nlI<\ll)S. which are not listed 'vaste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as all accessory metal in uranium ores
and concentrates, which are not listed waste sources.
COBALT
Commercial Commercial Non·Specific
Chemicals Chemicals Sources
Acutely Toxic Acutely FList
UList Hazardous
PList
NONE
NONE
NONE
IRON
Commercial Commercial Non-Specific
Chemicals Chemicals Sources
Acutely Toxic Acutely FList
UList Hazardous
PList
NONE
NONE
NONE
LEAD
Commercial Commercial Non-Specific
Chemicals Chemicals Sources
Acutely Toxic Acutely FList
UList Hazardous
PList
U 144
lead acetate
U 145
lead phosphate
UI46
lead subacetate
PlIO
Tetraethyl lead
TABLE 2 (Rev. 0): SUMMARY OF POTENTIAL RCRA LISTINGS
IN 40 CFR 261 and APPENDIX VII
ASSOCIATED WITH METALS IN SFC DEWATERED SLUDGE
K090 -
Emission control dust or sludge
from ferrochromium silicon
production
Specific Industrial Uses and Sources of U or P
Sources Listed Element or Compound
KList
--
---
NONE --
Specific Industrial Uses and Sources of U or P
Sources Listed Element or Compound
KList
--.
-. --I NONE --'
Specific Industrial Uses and Sources of U or P
Sources Listed Element or Compound
KList
Textile dyeing, chrome pigments, gold
cyanide leaching, lab reagent, hair dye.
May be present as antifoulant in paints,
waterproofing, varnishes.
Stabilizing agent added to plastic resins.
Decolorizing agent added to sugar
solutions in food products.
Synthesized solely as a gasoline
anti-knock additive.
Page 7
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
Is This Listing Applicable to
SFC Sludge'!
No U Listings.
No P Listings.
No F Listings.
No K Listine:s.
Is This Listing Applicable to
SFC Sludge?
No U Listings.
No P Listings.
No F Listings.
No K Listings.
Is This Listing Applicable to
SFC Sludge?
No. There would be no reason for this compound to be
present as pure product, byproduct, or off-spec product
on site.
No. There would be no reason for this compound to be
present as pure product, byproduct, or off-spec product
on site.
No. There would be no reason for this compound to be
present as pure product, byproduct, or off-spec product
on site.
No. There would be no reason for this compound to be
present as pure product, byproduct, or off-spec product
on site.
TABLE 2 (Rev. 0): SUMMARY OF POTENTIAL RCRA LISTINGS
IN 40 CFR 261 and APPENDIX VII
ASSOCIATED WITH METALS IN SFC DEWATERED SLUDGE
F035 -
Wood treating wastewater
F037 .-
Refinery oil/water separator solids
F038 -
Refinery secondary oil/water
separator solids
F039 --
Leachates from land disposal of
wastes F20 to F22 and F26 to F28
1<.002 --
Wastewater treatment sludge from
production of chrome yellow
pigment
K003 --
Wastewater treatment sludge from
production of chrome molybdate
orange pigment
KOO5 --
Wastewater treatment sludge from
production of chrome green
pigment
K046 -
Wastewater treatment sludge from
production of lead based
explosivejnitiators
K048 -
Petroleum refining dissolved air
flotation ("DAF') solids
K049 --
Petroleum refining slop oil
emulsion solids
K051 --
Petroleum refining API separator
solids
K052 Petroleum refining leaded .-
tank bottoms
K06l --
Steel electric furnace emission
. control dust/sludge
K062 -
Iron and steel manufacturing
pickle liquor
K064 -
Acid plant blowdown thickener
slurry/sludge from primary copper
production blowdown
Page 8
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also lead is
present primarily as an accessory metal in the tantalum
ores, which is not a listed waste source .
.. No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and C'Onc.entmtl!S., which ll1t! not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources .
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
LITHIUM
Commercial Commercial Non-Specific
Chemicals Chemicals Sources
Acutely Toxic Acutely FList
UList Hazardous
PList
NONE
NONE
NONE
-
MAGNESIUM
Commercial Commercial Non-Specific
Chemicals Chemicals Sources
Acutely Toxic Acutely FList
UList Hazardous
PList
NONE
NONE
NONE
MANGANESE
Commercial Commercial Non-Specific
Chemicals Chemicals Sources
Acutely Toxic Acutely FList
UList Hazardous
P List
NONE
TABLE 2 (Rev. 0): SUMMARY OF POTENTIAL RCRA LISTINGS
IN 40 CFR 261 and APPENDIX VII
ASSOCIATED WITH METALS IN SFC DEWATERED SLUDGE
K069 --
Emission control dust/sludge from
secondary lead smelting
K086 --Solvent, caustic and water wash
sludges from ink formulation
KIOO ---
Waste solution from acid leaching
of emission control dust/sludge
from secondary lead smelting
Specific Industrial Uses and Sources of U or P
Sources Listed Element or Compound
KList
-
---
NONE -------
Specific Industrial Uses and Sources of U or P
Sources Listed Element or Compound
KList
--
--
-
NONE -
Specific Industrial Uses and Sources of U or P
Sources Listed Element or Compound
KList
-
Page 9
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
-
Is This Listing Applicable to
SFC Sludge?
No U Listings I
No P Listings
No F Listings
I
_J-Io K Listings I
Is This Listing Applicable to
SFC Sludge?
No U Listings
No P Listings
No F Listings
No K Listings
Is This Listing Applicable to
I SFC Sludge?
I
I
No U Listings
I --
Pl96
Manganese
dimethyldithio
carbamate
NONE
MERCURY
Commercial Commercial Non-Specific
Chemicals Chemicals Sources
Acutely Toxic Acutely FList
UList Hazardous
PList
Ul5l
Mercury metal
Hg
P065 Mercury
Fulminate
P092
Acetato-O-
phenyl mercury
or
phenyl mercuric
acetate
NONE
TABLE 2 (Rev. 0): SUMMARY OF POTENTIAL RCRA LISTINGS
IN 40 CFR 261 and APPENDIX VII
ASSOCIATED WITH METALS IN SFC DEWATERED SLUDGE
Primarily as a pesticide.
-
NONE
Specific Industrial Uses and Sources of U or P
Sources Listed Element or Compound
KList
Dental amalgams, organic and inorganic
reaction catalyst, cathodes for chlorine!
caustic production cells, mirror coating,
vapor and arc lamps, nuclear power
reactors, boiler fluids. Also present in
instruments and used in extractive
metallurgy.
Due to relatively high detonation velocity,
used primarily as an explosive initiator in
military explosives. Too unstable for most
other uses.
Used as a fungicide, anti-mildew agent,
and as a topical spermicide
-
K07l -
Brine purification muds from
mercury cell chlorine production
I K106 -
Wastewater treatment sludge from
mercury cell chlorine production
Page 10
No. There would be no reason for this compound to be
present as pure product, byproduct. or off-spec product
on site.
No F Listings
No K Listings
Is This Listing Applicable to
SFC Sludge?
No. There would be no reason for this compound to be
present as pure product. byproduct. or off-spec product
on site.
No. There would be no reason for this compound to be
present as pure product. byproduct, or off-spec product
on site.
No. There would be no reason for this compound to be
present as pure product, byproduct, or off-spec product
on site.
No F Listings
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates, which are not listed waste sources.
No. SFC material is not from this industry. Also it is
present primarily as an accessory metal in uranium ores
and concentrates. which are not listed waste sources.
MOLYBDENUM
Commercial Commercial
Chemicals Chemicals
Acutely Toxic Acutely
UList Hazardous
PList
NONE
NONE
NICKEL
Commercial Commercial
Chemicals Chemicals
Acutely Toxic Acutely
UList Hazardous
PList
NONE
P073
Nickel carbonyl
P074
Nickel Cyanide
POTASSIUM
Commercial Commercial
Chemicals Chemicals
Acutely Toxic Acutely
UList Hazardous
PList
NONE
P098
Potassium
cvanide
P099
Potassium silver
cyanide
Non·Specific
Sources
FList
NONE
Non-Specific
Sources
FList
FOO6
TABLE 2 (Rev. 0): SUMMARY OF POTENTIAL RCRA LISTINGS
IN 40 CFR 261 and APPENDIX VII
ASSOCIATED WITH METALS IN SFC DEWATERED SLUDGE
Specific Industrial Uses and Sources of U or P
Sources Listed Element or Compound
KList
----.
NONE
Specific Industrial Uses and Sources of U or P
Sources Listed Element or Compound
KList
--
Electroplated nickel coatings, reagent
chemical
Metallurgy. electroplating
-
Wastewater treatment sludge from
electroplating
NONE -
Non-Specific Specific Industrial Uses and Sources of U or P
Sources Sources Listed Element or Compound
FList KList
-
Extraction of gold and silver from ores,
reagent in analytical chemistry,
insecticide, fumigant, electroplating.
Silver plating, bactericide. antiseptic.
NONE
K16! Dithiocarbamate production
Metam-sodium
Purification solids, baghouse dust
and sweepings form
dithiocarbamate production.
Page 11
Is This Listing Applicable to
I SFC Sludge?
No U Listin!!s
No P Listings
No F Listings
No KListings
Is This Listing Applicable to
SFC Sludge?
No U Listings
No. There would be no reason for this compound to be
present as pure product, byproduct, or off-spec product
on site.
No. There would be no reason for this compound to be
present as pure product. byproduct. or off-spec product
on site.
No K Listin.gs
Is This Listing Applicable to
SFC Sludge?
No U Listings
No. There would be no reason for this compound to be
present as pure product, byproduct, or off-spec product
on site.
No. There would be no reason for this compound to be
present as pure product. byproduct, or off-spec product
on site.
No F Listings
No K Listings
RADIUM
Commercial Commercial Non-Specific
Chemicals Chemicals Sources
Acutely Toxic Acutely FList
UList Hazardous
PList
NONE
NONE
NONE
SEL6NIUM
Commercial Commercial Non-Specific
Chemicals Chemicals Sources
Acutely Toxic Acutely FList
UList Hazardous
PList
U204
Selenious acid
or
selenium dioxide
U205
Selenium sulfide
or selenium
disulfide
PI03
Selenourea
P1l4
Selenious acid
dithallium salt,
Selenious acid
dithallium salt,
Thallium
selenide,
I Thallium
selenite,
Ancimidol
NONE
SILVER
Commercial Commercial Non-Specific
Chemicals Chemicals Sources
Acutely Toxic Acutely FList
UList Hazardous
PList
NONE
TABLE 2 (Rev. 0): SUMMARY OF POTENTIAL RCRA LISTINGS
IN 40 CFR 261 and APPENDIX VII
ASSOCIATED WITH METALS IN SFC DEWATERED SLUDGE
Specific Industrial Uses and Sources of U or P
Sources Listed Element or Compound
KList
--
NONE
Specific Industrial Uses and Sources of U or P
Sources Listed Element or Compound
KList
Selenious acid and its salts are used for
cold blackening of metal parts for model
building and decorative finishes.
Preparation of topical dermal and scalp
medications.
Production of dimethyl selenourea for
safety glass coatings
Selenious acid and its salts are used for
cold blackening of metal parts for model
building and decorative finishes.
I
--
NONE --
Specific Industrial Uses and Sources of U or P
Sources Listed Element or Compound
KList
-
Page 12
Is This Listing Applicable to
SFC Sludge?
No U Listings
No P Listings
No F Listings
No K Listings
Is This Listing Applicable to
SFC Sludge?
No. There would be no reason for this compound to be
present as pure product or byproduct on site.
No. There would be no reason for this compound to be
present as pure product or byproduct on site.
No. There would be no reason for this compound to be
present as pure product or byproduct on site.
No. There would be no reason for this compound to be
present as pure product or byproduct on site.
No F Listings
No K Listings
Is This Listing Applicable to
SFC Sludge?
No U Listings
P099
Potassium bis
(cyano-c) (1)
argentate
Silver potassium
cvanide
PI04
Silver cyanide
NONE
SODIUM
Commercial Commercial Non-Specific
Chemicals Chemicals Sources
Acutely Toxic Acutely FList
UList Hazardous
PList
U236
3,3'-[(3,3'-
dimethyl[ I, I ' -
biphenyl]-4,4' -
diyl)bis(azo)bis[5-
amino-4-hydroxy]-
,tetrasodium salt
P058
F1uoroacetic acid
sodium salt
PI05
Sodium azide
PI06
Sodium Cyanide
NONE
TABLE 2 (Rev. 0): SUMMARY OF POTENTIAL RCRA LISTINGS
IN 40 CFR 261 and APPENDIX VII
ASSOCIATED WITH METALS IN SFC DEWATERED SLUDGE
Silver plating, bactericide, antiseptic
Used in silver plating.
-
NONE -
Specific Industrial Uses and Sources of U or P
Sources Listed Element or Compound
KList
-
Rodenticide
Air bag inflator, intermediate in explosive
manufacture, preservative in diagnostic
medicines.
Manufacture of dyes, pigments, nylon,
chelating compounds, insecticides,
fumigants. Extraction of gold and silver
from ores, electroplating, metal cleaning,
heat treatment, ore flotation.
KI61 Dithiocarbamate production
Metam-sodium
Purification solids, baghouse dust
and sweepings form
dithiocarbamate production.
Page 13
No. There would be no reason for this compound to be
present as pure product, byproduct, or off-spec product
on site.
No. There would be no reason for this compound to be
present as pure product, byproduct, or off-spec product
on site.
No F Listings i
No K Listings
Is This Listing Applicable to
SFC Sludge?
No. There would be no reason for this compound to be
present as pure product, byproduct, or off-spec product
on site.
No. There would be no reason for this compound to be
present as pure product, byproduct, or off-spec product
on site.
No. There would be no reason for this compound to be
present as pure product, byproduct, or off-spec product
on site.
No. There would be no reason for this compound to be
present as pure product, byproduct, or off-spec product
on site.
No F Listings
No. There would be no reason for this compound to be
present as pure product, byproduct, or off-spec product
on site.
STRONTIUM
Commercial Commercial Non-Specific
Chemicals Chemicals Sources
Acutely Toxic Acutely FList
UList Hazardous
PList
NONE
NONE
NONE
----
THALLIUM
Commercial Commercial Non-Specific
Chemicals Chemicals Sources
Acutely Toxic Acutely F List
UList Hazardous
PList
U214
Thallium (I)
acetate
U215
Thallium (I)
Carbonate
U216
Thallium chlOlide
U217
Thallium (I)
nitrate
P114
Selenious acid
dithallium salt,
Thallium
selenide,
Thallium
selenite.
Ancimidol
P1I5
Sulfuric acid
dithallium salt
NONE
TABLE 2 (Rev. 0): SUMMARY OF POTENTIAL RCRA LISTINGS
IN 40 CFR 261 and APPENDIX VII
ASSOCIATED WITH METALS IN SFC DEWATERED SLUDGE
Specific Industrial Uses and Sources of U or P
Sources Listed Element or Compound
KList
---
NONE
Specific Industrial Uses and Sources of U or P
Sources Listed Element or Compound
KList
High specific gravity solutions for ore
flotation.
Laboratory standard for analysis for
carbon disulfide, synthesis of artificial
diamonds.
Chlorination catalyst. sun lamp monitors.
Analytical standard, green-fire
pyrotechnics.
Selenious acid and its salts are used for
cold blackening of metal parts for model
building and decorative finishes.
Pesticide, ant-killer
-
K178 -.
Residues from manufacturing and
storage of ferric chloride from
acids from titanium dioxide
production
Page 14
Is This Listing Applicable to
SFC Sludge'?
No U Listings
No P Listings
No F Listings
No K Listings
Is This Listing Applicable to
SFC Sludge?
No. There would be no reason for this compound to be
present as pure product, byproduct. or off-spec product
on site.
No. There would be no reason for this compound to be
present as pure product, byproduct, or off-spec product
on site.
No. There would be no reason for this compound to be
present as pure product, byproduct, or off-spec product
on site.
No. There would be no reason for this compound to be
present as pure product. byproduct, or off-spec product
on site.
No. There would be no reason for this compound to be
present as pure product. byproduct, or off-spec product
on site.
No. There would be no reason for this compound to be
present as pure product, byproduct, or off-spec product
on site.
No F Listings
No. SFC material is not from this industry. Also,
thallium is present primarily as an accessory metal in the
tantalum ores, which is not a listed waste source.
THORI UM -
Commercial Commercial Non-Specific
Chemicals Chemicals Sources
Acutely Toxic Acutely FList
UList Hazardous
P List
NONE
NONE
NONE
VANADIUM
Commercial Commercial Non-Specific
Chemicals Chemicals Sources
Acutely Toxic Acutely FList
UList Hazardous
PList
NONE
Pl20
Vanadium
pentoxide
NONE
ZINC
Commercial Commercial Non-Specific
Chemicals Chemicals Sources
Acutely Toxic Acutely FList
UList Hazardous
PList
U249
Zinc phosphide
( 10 wI. % or less)
Pl21
Zinc cyanide
PI22
Zinc phosphide
(greater than I 0
wt.%)
P205
Zinc dimethyl
dithiocarbamate,
Ziram
NONE
TABLE 2 (Rev. 0): SUMMARY OF POTENTIAL RCRA LISTINGS
IN 40 CFR 261 and APPENDIX VII
ASSOCIATED WITH METALS IN SFC DEWATERED SLUDGE
Specific Industrial Uses and Sources of U or P
Sources Listed Element or Compound
KList
--
NONE ------ -
Specific Industrial Uses and Sources of U or P
Sources Listed Element or Compound
KList
--
NONE
Specific Industrial Uses and Sources of U or P
Sources Listed Element or Compound
KList
Rodenticide
Metal plating, chemical reagent,
insecticide.
Rodenticide
Fungicide, accelerator in rubber synthesis.
-
KI61 Rodenticide
Ziram pesticides
Page 15
Is This Listing Applicable to
SFC Sludge?
No U Listings
No P Listings
No F Listings
l'Jo K Listings
Is This Listing Applicable to
SFC Sludge?
No U Listings
No. There would be no reason for this compound to be
present as pure producl, byproduct, or off-spec product
on site.
No F Listings
No K Listings
Is This Listing Applicable to
SFC Sludge?
No. There would be no reason for this compound to be
present as pure product, byproduct, or off-spec product
on site.
No. There would be no reason for this compound to be
present as pure product, byproduct, or off-spec product
on site.
No. There would be no reason for this compound to be
present as pure product, byproduct, or off-spec product
on site.
No. There would be no reason for this compound to be
present as pure product, byproduct, or off-spec product
on site.
No F Listings
No. SFC material is not from this industry. Also, zinc
is present primarily as an accessory metal in the
tantalum ores, which is not a listed waste source.
ZIRCONIUM
Commercial Commercial Non·Specific
Chemicals Chemicals Sources
Acutely Toxic Acutely FList
UList Hazardous
PList
NONE
NONE
NONE
TABLE 2 (Rev. 0): SUMMARY OF POTENTIAL RCRA LISTINGS
IN 40 CFR 261 and APPENDIX VII
ASSOCIATED WITH METALS IN SFC DEWATERED SLUDGE
Specific Industrial Uses and Sources of U or P
Sources Listed Element or Compound
KList
----
NONE
Page 16
Is This Listing Applicable to
SFC Sludge'?
No U Listings
No P Listings
No F Listings
No K Listings
ATTACHMENT 5
Review of Chemical Contaminants in SFC Uranium Material to Determine Worker Safety
and Environmental Issues and Chemical Compatibility at the White Mesa Mil
Technical Memorandum
To: David C. Frydenlund From: Jo Ann Tischler
Company: QeRfseR-MiReSEnergy Fuels Resources
(USA) Ge$1 nco
Date: Deoember 15, 2011 July 15,
2013
Re:
CC:
Review of Chemical Contaminants in
Sequoyah Fuels Uranium Material to
Determine Worker Safety and
Environmental Issues and Chemical
Compatibility at the White Mesa Mi" Project #: ----------------------
1.0 Introduction
This report summarizes the characterization of the Sequoyah Fuels Corporation ("SFC")
Uranium Material (the "Uranium Material"), also referred to as the dewatered raffinate
sludge to be transported from the SFC Gore, Oklahoma facility, to determine whether
processing the Uranium Material at the ·QeAis~>A--Mffies.-El1erqy Fuels Resources (USA)
Ge$lnc. ('~aA-iSGFlEFR I") White Mesa Mi" (the "Mi"") may pose any worker safety or
environmental hazards, or may be incompatible with the Mill's existing tailings system .
The results wi" provide information to DenisonEFRI to determine the requirements, if
any, for changes to worker safety practices, or potential incompatibilities to the Mi" for
the processing of Uranium Material as an alternate feed material. This report wi" also
provide comparison of constituents of the Uranium Material and the DenisonEFRI
groundwater ("GW") monitoring program to identify any constituents which are not
covered under the DenisonEFRI GW monitoring program and whether these additional
parameters need to be added to the sampling requirements.
The following questions were considered for the evaluation of potential safety and
environmental hazards and compatibility with the Mill's tailings system and GW
monitoring requirements:
1) Wi" any constituents of the Uranium Material volatilize at the known
conditions on the Mi" site or in the Mi" circuits? If so, wi" they create any
potential environmental, worker health, or safety impacts?
2) Wi" the Uranium Material or any of its constituents create a dust or off-gas
hazard at the known conditions on the Mill site or in the Mill circuit? If so, wi"
they create any potential environmental, worker health, or safety impacts?
3) Wi" any constituents of the Uranium Material react with other materials in the
Mi" circuits?
4) Wi" any constituents of the Uranium Material create any impacts on the
tailings system?
5) Does the Uranium Material contain any constituents that are not present in
the current Mill GW monitoring program and not sufficiently represented by
the Mill's groundwater monitoring analyte list and need to be added to the
analyte list?
6) What, if any, limitations on feed acceptance criteria or added operational
controls are recommended in connection with processing the Uranium
Material at the Mill?
An evaluation of the regulatory status of the Uranium Material relative to the Resource
Conservation and Recovery Act ("RCRA") regulations is provided in a separate technical
memorandum.
2.0 Basis and Limitations of This Evaluation
The Uranium Material to be processed at the Mill consists solely of the dewatered
raffinate sludge currently stored on site at the Gore Facility.
The following contamination evaluation is based on:
The evaluation in this memorandum is based on information from the following sources:
1. SFC RCRA Facility Investigation Report ("RFI") (1997).
2. Current and historic SFC Uranium Material analytical data.
3. Interviews with Sequoyah Fuels personnel in March 2010.
4. EFRI (formerly Denison} Protocol for Determining Whether Alternate Feeds Are
Listed Hazardous Wastes (Denison, November 1999).
5. Radioactive Material Profile record ("RMPR") for the SFC Uranium Material
(February 2010).
6. Basis of Hazardous Material and Waste Determinations from the RMPR
(February 2010)
7. Affidavit of John Ellis, SFC President (June 2010).
8. Current technical literature from the internet and other sources on performance of
liner materials
3.0 Site History and Background
The SFC Gore, Oklahoma facility (the "Facility" or the "Site") is a former uranium
conversion facility that operated from 1970 to 1993. The facility was constructed and
operated by SFC, as a subsidiary of Kerr-McGee Nuclear Corporation. In 1983 Kerr-
McGee Nuclear Corporation split into Quivira Mining Corporation and SFC, which
maintained control of the Gore Facility. SFC was sold to General Atomics Corporation in
1988 and continued to operate the facility until 1993.
From 1970 to 1993, the facility chemically converted uranium ore concentrates
(yellowcake) to uranium hexafluoride under U.S. Nuclear Regulatory Commission
("NRC") Source Materials License Number SUB-1010. From 1987 to 1993, the facility
also converted depleted uranium hexafluoride into depleted uranium tetrafluoride in a
different circuit. The Uranium Material consists only of residuals from the conversion of
natural uranium yellowcake to uranium hexafluoride.
3.1 Description of Process which Generated the Uranium Material
This yellowcake conversion process included two primary purification steps: digestion
followed by solvent extraction. Digestion occurred by dissolving the uranium in nitric
acid. The resulting slurry was subjected to solvent extraction using tributyl phosphate
diluted with n-hexane. Process conditions were controlled to extract uranium into the
organic phase. The milling impurities remained in the aqueous phase, a dilute nitric acid
mixture termed raffinate.
The aqueous raffinate stream is primarily a solution of nitric acid, metallic salts, and
trace quantities of uranium and radioactive transformation products of natural uranium,
primarily Th-230 and Ra-226. The aqueous raffinate stream was combined with spent
sodium hydroxide from nitrous oxide scrubber systems and waste sodium carbonate
solutions. The untreated raffinate stream from solvent extraction was pumped to an
impoundment and allowed to cool. Anhydrous ammonia was added to the raffinate
solution to convert the dilute nitric acid to ammonium nitrate. The final treated raffinate
solution was stored in surface impoundments prior to use as an ammonium nitrate
fertilizer.
Generation of Raffinate Sludge
The addition of the anhydrous ammonia also increased the pH of the raffinate solution
causing the metallic salts and trace quantities of uranium, thorium, and radium to
precipitate and settle out in the impoundments as raffinate sludge.
Per the RMPR, the chemical reagents used in the above processes included:
• nitric acid
• tributyl phosphate
• n-hexane
• anhydrous ammonia
• barium chloride
• spent sodium hydroxide
• waste carbonate solutions
• recovered weak acids
The presence of residuals of some of these compounds and/or their reaction byproducts
would be expected in the Uranium Material, as discussed in the sections below.
The raffinate sludge was transferred by slurry to other storage ponds as necessary. The
raffinate sludge was accumulated and stored in several impoundments on site, including
Clarifier A basins and Pond 4. No other materials were combined with the stored sludge.
The raffinate sludge was eventually consolidated in the Clarifier A basins to support
decommissioning Pond 4 and dewatering of the raffinate sludge.
Treatment of Raffinate Solution Phase
The treated raffinate solution was decanted to another impoundment for further
treatment with barium chloride to remove trace levels of radium through co-precipitation.
The radium co-precipitate was periodically combined with the raffinate sludge in the
other impoundments.
Preparation and Packaging of Dewatered Sludge
The raffinate sludge was slurried from Clarifier A basins and processed through a 225
psi filter press to remove entrained water. The dewatered sludge was placed in one
cubic yard polypropylene bags. Approximately 11,000 tons (wet weight basis) or 5,000
tons (dry weight basis) or 11,500 bags are stored on site awaiting final recycling or
disposal.
4.0 Assumptions Regarding White Mesa Mill Processing of the Uranium Material
This evaluation was based on the following process assumptions:
1. The Mill will process the Uranium Material in the main circuit either alone or in
combination with natural ores or other alternate feeds.
2. The Uranium Material will be delivered to the Mill by truck in SuperSaks of
approximately 0.95 tons each, and approximately 21 bags per truckload. The
bags will be shipped in truck trailers with poly-lined bottoms and sides, either
box-style trailers, or flatbed style trailers with sidewalls and tarp covers.
3. The Supersaks will be unloaded from the trucks onto the ore pad for temporary
storage until the material is scheduled for processing.
4. The Uranium Material will be added to the circuit in a manner similar to that used
for the normal processing of conventional ores and other alternate feed
materials. It will either be dumped into the ore receiving hopper and fed to the
SAG mill, run through an existing trommel or grizzly, before being pumped to
Pulp Storage, or may be fed directly to Pulp Storage.
5. The Mill does not anticipate any significant modifications to the leaching circuit or
recovery process areas for the processing of the Uranium Material.
6. The Uranium Material may be processed in combination with other approved
alternate feed materials.
7. Tailings from processing of the Uranium Material will be sent to Cell 4A or Cell
48 or a comparable new tailings cell.
5.0 Chemical Composition of the Uranium Material
Physical and chemical properties of the raffinate sludge have been determined at
different times to support site characterization activities and treatability studies. The
results of those determinations were described in several reports prepared subject to the
authority of the State of Oklahoma Department of Environmental Quality and/or the NRC
in the process of site decommissioning, including the RCRA Facility Investigation Report
(RFI) and the Site Characterization Report (SCR).
SFC determined the list of constituents for analyses based on the US EPA May 1989
Interim Final RCRA Facility Investigation Guidance (the "RFI Guidance"). Analyses were
conducted for the constituents specified in the RFI Guidance for the mining industry, the
inorganic chemicals industry, and the non-ferrous metals industry, with the following
exceptions:
1. Analyses were performed for two additional metals, calcium and molybdenum,
beyond those listed in the RFI Guidance
2. Analysis was not performed for organochlorine pesticides. Pesticides were not
produced, stored in bulk, spilled or disposed at the Facility. Organochlorine
pesticides would only be present in site soils at residual levels typical of their
intended end use.
3. Samples were not analyzed for dibenzo(c,g) carbazole, dibenzo (a,h) pyrene,
dibenzo (a,i) pyrene and chloroacetaldehyde. None of these compounds were
produced, used or stored at the Facility nor are they breakdown products from any
chemicals used at the Facility.
The selection of constituents, numbers of samples, and characterizations enumerated
above were approved by and performed subject to the authority of the State of
Oklahoma Department of Environmental Quality and/or the NRC in the process of site
decommissioning. Characterization of the Uranium Material comprised Rffie-ten
analyzed samples from the locations and conditions identified in Table 1.
The sampling was representative of a continuous process stream under the control of
the generator from a process which did not vary appreciably over time and was accepted
by the Oklahoma Department of Environmental Quality and the NRC as indicated by
these agencies' approval of the respective closure plan documents developed based on
the characterization. All analyses were performed by laboratories possessing State of
Oklahoma and/or NELAC certification for the analyses performed.
As a result, these studies provide sufficiently representative characterization to assess
the regulatory status, worker safety environmental hazards, and chemical and
processing properties of the Uranium Material.
I
I
I
I
I
Table 1: Summary of Analytical Studies on Sequoyah Fuels Uranium Material
Condition of Sample Name(s) Analyses Number of Used in
Uranium Samples Taifings
Material Mass
Balance
Table
Prior to Raw Sludge or Metals, 4 No
dewatering Raffinate Sludge or radionuclides,
Pond 4 -1994 ammonia, nitrate,
fluoride
Leachate from Raw Sludge Leachate Metals, 1 composite No
Uranium or Pond 4 Composite -radionuclides, of 4 samples
Material 1994 ammonia.£§.
nitrogen, nitrate,
fluoride
PFieF te Raffinate Sludge or VOCs, SVOCs 1 No
dewateFing Basin 1 of Clarifier A -
1995
Dewatered Dewatered Sludge -Metals, 1 Yes
Uranium 2003 radionuclides,
Material ammonia, nitrate,
fluoride
Dewatered Dewatered Sludge -Fluoride, nitrate + 1 Yes
Uranium 2013 nitrite as
Material nitrogen,
ammonia as
nitroaen
Water removed Dewatering Filtrate -Metals, 1 No
from Uranium 2003 radionuclides,
Material ammonia, nitrate,
fluoride
Leachate from Dewatered Sludge Metals, 1 No
dewatered Leachate -2003 radionuclides,
Uranium ammonia, nitrate,
Material fluoride
5.1 Organic Constituents
5.1.1 Volatile Organic Compounds
Based on knowledge of the process controlled by the generator, no organic hazardous
constituents were produced, used, or stored at the Facility. As expected, analyses for all
volatile and semi-volatile constituents were non-detectable with the exception of 2-
butanone (methyl ethyl ketone) and 2-hexanone.
Each of these ketones were detected at levels very near its practical quantitation limit -
0.3 mg/kg versus a pal of 0.1 for 2-butanone, and 0.08 versus a pal of 0.05 for 2-
hexanone. Both of these ketones are common laboratory solvents and are also present
in adhesives, marker pens, and inks associated with the sampling process. Based on
the foregoing information, the detection of both of these compounds should be
considered as anomalous or as due to laboratory or sampling influences.
Both of these ketones are highly volatile. Even if they were present at these trace levels
in the Uranium Material at the Facility in the pond sludges, the filling, shipping,
unloading, and emptying of the SuperSaks would volatilize these compounds to non-
detectable levels at the Mill.
5.1.2 Semi-volatile Organic Compounds
No semi-volatile constituents were detected in the Uranium Material.
5.2 Inorganic Constituents
Analyses of inorganic constituents is provided in the analytical reports included with the
RMPR and summarized in Attachments 0.1 of the RMPR.
5.2.1 Non-Metal Inorganic Compounds
AmmoniaasN
Anhydrous ammonia was added to the residuals of the conversion process to recover
dilute nitric acid as ammonium nitrate. Ammonia was added at controlled rates sufficient
to react and convert the dilute nitric acid to a marketable ammonium nitrate fertilizer
product. AmmeRia-was-Aet-a-Ra~n the raw-.er do 'Nato rod slud~lt-V.,as not
expected to be pFesont abovo trace leveJ&..Ammonia was analyzed in one sample of
dewatered raffinate sludge In 2..0 13. and Was detecled in that sample at 5,210 mqJkq
NitrateJNitrite as N
Nitrate/nitrite compounds entered the Facility process due to the use of nitric acid in the
uranium digestion step. +t:\e--a-ver-a§e-I~te-I&~I-(.afH.litFe§eAj-ana~El-ln the row
sltldge s3Alpies 'HasA2,40G-mWk§-~Fi~ewatej:ir=l§.,--N*ato \'\,a6 nffi.-af1aly~
€le'.Yatered sludge primarily beoauso it was not expocted to be pwsent abGVe4!=a€e
levels. Nitrate was reacted with anhydrous ammonia to produce the ammonium nitrate
fertilizer mentioned above. Nitrate plus nitrite as N was ane Iyzed in ol1e sample of
dewatered raffinate sludge in 2013 and was detected in that sample at 4.580 mg/ka.ffi
a€l€f.l.tion, nitr:ate Is extr·emeiy-seh:!£:»e--j.A-AeafJy--aU--rnineraJ torms. If any tmEr-e I~
ffiA1a~ned in the-r~dge;-4.t--wGwd parlilieA-ifl-tl~~pros6 pFimaFlly to the--mt-rate
{~~YSj-~hase, not tho dewatGfe~Q9e-FlAase.
Phosphorus
Phosphorus is present as a residual of the tributyl phosphate used in the uranium
hexafluoride extraction step. Phosphorus, which will be present in the phosphate form,
was analyzed at 19,600 mg/kg in the dewatered sludge that comprises the Uranium
material. +his level is !HeU-within the-Iovel pte-5eRHA-9ther alternate feetls--a1fe.a9.y
~ove€l-f.eF-J3fSOOS$j ~the-Mm;-WRiGJ:l-RavO rangecl-as-J:H~h 3S 262,000 mg/kg ef
phosphorus in the phosphate form.
Ruoricles
Fluoride was analyzed in one sample of dewatered raffinate sludge in 2013. The
average detected fluoride level analyzed in the raw sludge samples was 23,118 44.100
mg/kg.:. prior to de'Natering. ~rido \NBS not aAalyzed in the dev.ratere~e--eF
dO'A'atoring hll~or. Fer GOASer!fati5rf1..;-i!-has-geeR-estimato~Re--ooRGemr-ai.feA
IfHAe--aowatBfed-S!uti~i~~¥al9Rt-tB-t-I=!~GefttFat-ier::Hr-H+le--FaW-Slooge. This
aS5~OOrHS-f)Vel:Jy-eeA-6efVaW/o bOGal::lse-f.I :lGf.f€le-is oxtremely-seh::lele-ift-f'RGfly-ffiiAeFa1
~~n in tho filter pross primaf+ly to (ho tiltfata ... {aq\:lee~t
.u~e-tleWa-tefeG-stbl~~J:l.ase-,-..NeA9t:AetOSS, to(4;.G ooFVati6m it has ~A assumaG-l:Rat
tho dewatered f.i.I.tf~lso contain 23,1 18 mg/l{g of flb/eriso . This-leval-f&--lrve-It
within the level ~resent in ffiher alteFAateie~Pi~fGVe€!-fef--J*G6eS6iA§-al4he
MUI, SUGA-as tAO FanS.teol-aUefnaro woe! malerial, whish Gonl=alned GenGeAtfalffiAs
ranging up to 396,000 mg/kg.
5.2.2 Metals
The three Uranium Material samples were analyzed for total metals, total alkali metals,
and total alkaline earth metals. According to the sampling results, 26 non-radioactive
metals and metalloids were present in the Uranium Material. These constituents can be
categorized based on their elemental characteristics and chemical properties as indicated
in Table 2.
Table 2: Classes of Metals in SFC Uranium Material
Class Component of the Uranium Material
Alkali Metals Lithium, Sodium, Potassium
Alkaline Earths Barium, Beryllium, Calcium, Magnesium,
Strontium
Cadmium, Chromium, Cobalt, Copper,
Transition Metals Iron, Manganese, Mercury, Molybdenum,
Nickel, Silver, Thallium, Vanadium, Zinc
Other Metals Aluminum, Lead
Metalloids Antimony, Arsenic, Selenium
With the exception of barium, all species listed in Table 2, above, are natural
constituents in uranium ores, are expected to be present in uranium concentrates
(yellowcake) processed at the Facility, and are expected to be present in sludges
precipitated from yellowcake impurities. Barium was introduced as barium chloride,
which was added to the raffinate solution for co-precipitation of radium.
The Uranium Material samples were not analyzed for their actual mineral composition,
that is, the compound form(s) in which each constituent is present. However, sufficient
process knowledge of the Facility process exists to reasonably assess the forms for
each constituents, as discussed under each class constituent, below.
Based on knowledge of the Gore plant process and pond treatment process, some
conclusions can be drawn about the mineral form of the metals identified in the
characterization analyses. These are discussed in the remainder of section 5.2.2 below.
None of the incompatibilities described below or in Table 3 are applicable to the
components as they will be present in the Uranium Material. None of the components
will be present in pure/reduced metal form or as pure metal oxides. None of the
fluoridated, sulfite, or cyanide, compound or hydroxylated (caustic forms) of the alkali
metals or alkaline earths are expected to be present. None of the components will be
exposed to any of the incompatible agents identified in the table.
Alkali Metals
The alkaline earths metals, lithium, sodium, and potassium are natural constituents in
uranium ores, are expected to be present in uranium concentrates (yellowcake)
processed at the Facility, and are expected to be present in sludges precipitated from
yellowcake impurities. All of the components are expected to be present in inert hydrate,
chloride, sulfate, or other soluble salt forms, compatible with the aqueous solutions in the
Mill's acid digestion and feed circuit. In addition, since all the constituents entered the
process in mineralized forms and were further reacted with mineral acids, none will be
present in pure or reduced metal form. Because the Uranium Material is approximately
pH neutral, none of the alkaline earths will be present in alkali hydroxide (caustic) forms;
all will have been precipitated as other salts or complexes. Since the pond materials are
wet or dewatered sludges that have not been fired or calcined, none of the alkaline
earths will be present as oxides.
Alkaline Earths
The alkali metals, beryllium, calcium, magnesium, and strontium, whether or not they
have been analyzed in specific ores processed at the Mill, are natural constituents in
uranium ores, are expected to be present in uranium concentrates (yellowcake)
processed at the Facility, and are expected to be present in sludges precipitated from
yellowcake impurities. E.g. strontium, while not specifically analyzed for in ores at the
Mill, is the 14th most abundant metal in the earth's crust and can be expected to be
present in natural soils, natural ores and product concentrates from natural ores. All of
the components are expected to be present in inert hydrate, chloride, sulfate, carbonate,
or other soluble salt forms, compatible with the aqueous solutions in the Mill's acid
digestion and feed circuit. Because the Uranium Material is approximately pH neutral,
none of the alkali metals will be present in hydroxides (caustic) forms; all will have been
precipitated as other salts or complexes. In addition, since all the constituents entered
the process in mineralized forms and were further reacted with mineral acids, none will
be present in pure or reduced metal form. Since the pond materials are wet or
dewatered sludges that have not been fired or calcined, none of the metals will be
present as oxides.
Barium is present as a result of the barium chloride added to the raffinate solution for co-
precipitation of radium prior to discharge at the Facility. Barium was used to form inert
non-reactive precipitates with radium.
Transition Metals
The transition metals, cadmium, chromium, cobalt, copper, iron, manganese, mercury,
molybdenum, nickel, silver, thallium, vanadium, zinc are expected to be present in
uranium concentrates (yellowcake) processed at the Facility, and are expected to be
present in sludges precipitated from yellowcake impurities. All of the components are
expected to be present in inert hydrate, chloride, sulfate, or other soluble salt forms,
compatible with the aqueous solutions in the Mill's acid digestion and feed circuit. In
addition, since all the constituents entered the process in mineralized forms and were
further reacted with mineral acids, none will be present in pure or reduced metal form .
Since the pond materials are wet or dewatered sludges that have not been fired or
calcined, none of the metals will be present as oxides.
Other Metals
The other metals, aluminum and lead are expected to be present in uranium
concentrates (yellowcake) processed at the Facility, and are expected to be present in
sludges precipitated from yellowcake impurities. All of the components are expected to
be present in inert hydrate, chloride, sulfate, or other soluble salt forms, compatible with
the aqueous solutions in the Mill's acid digestion and feed circuit. In addition, since all
the constituents entered the process in mineralized forms and were further reacted with
mineral acids, none will be present in pure or reduced metal form. Since the pond
materials are wet or dewatered sludges that have not been fired or calcined, none of the
metals will be present as oxides.
Metalloids
The metalloids, antimony, arsenic, and selenium, are expected to be present in uranium
concentrates (yellowcake) processed at the Facility, and are expected to be present in
sludges precipitated from yellowcake impurities. All of the components are expected to
be present in inert hydrate, chloride, sulfate, or other soluble salt forms, compatible with
the aqueous solutions in the Mill's acid digestion and feed circuit. In addition, since all
the constituents entered the process in mineralized forms and were further reacted with
mineral acids, none will be present in pure or reduced metal form. Since the pond
materials are wet or dewatered sludges that have not been fired or calcined, none of the
metalloids will be present as oxides.
5.3 Potential Effects in Mill Process
The Uranium Material is a near-neutral byproduct of dewatering precipitated aqueous
sludges. The metals in the Uranium Material are expected to be in the form of metal
hydrates, hydroxides, sulfates, chlorides, and other inert salts, minerals, and complexes
compatible with the aqueous and aqueous acid solutions in the Mill's feed area and
leach circuits. The cations and metals in natural ores are also present in hydrate,
sulfate, chloride, and other inert salt, mineral, and complex forms.
Most of the metal species resulting from natural ores in the Uranium Material are present
at parts per million ("ppm") levels or lower (or at percent levels in the highest case). The
Uranium Material is a semi-moist filter cake with approximately 55% moisture/45%
solids. Similar to natural ores, it may be introduced into the Mill through the grizzly or a
trommel for size reduction, at which time it would be contacted with water sprays, further
reducing the relative solids content (and therefore the concentrations of constituents).
The concentrations of these constituents will be further reduced by introduction into the
leach circuit, where they will be present at fractional ppm levels or lower in large
volumes of aqueous acid solution. These constituents will be processed in the same
manner as natural uranium ores processed at the Mill and will be discharged to the Mill
tailings system just as the uranium ores currently are.
The majority of the soluble mineral salts will be converted to sulfate salt forms in the
leach system. The insoluble forms will be precipitated with the solids removed from the
Mill circuit.
All the known Uranium Material components in their anticipated mineral states are
compatible with aqueous sulfuric acid, which will be used for leaching the Uranium
Material, and any other chemicals and materials to which they may be exposed in the
Mill following the leach circuit.
Since the metal salts are expected to be converted to insoluble sulfates or other
insoluble precipitates, it can be assumed that the non-uranium constituents that enter
the leach system will leave the leach system, proceed no further than the Counter-
current Decantation ("CCD") step or Tank 11 A or 11 B, and be discharged from the circuit
to the tailings.
Some of the metal hydroxides and metal sulfates, in the forms in which they will enter
the Mill, are known to decompose at high temperatures, breaking down into volatile
oxide forms (such as As20 s decomposing to a trioxide). However, as described above,
1) The metal salts and other cation salts will be short-lived in the process, as they
will be converted into sulfates in the leach acid.
2) The same types of metal sulfates have been introduced into the Mill in thousands
of tons of natural ore, and similarly processed with no exposure to, or effects
from, high temperature,
3) Like natural ores, the metal salts will not be exposed to any conditions that can
produce gaseous byproducts.
The sulfate forms are stable and non-reactive and will be precipitated from the circuit in
post-leach steps and discharged to the tailings system.
5.3.1 Alkaline Earth Metals
Although in some circumstances, the introduction of oxides of the alkaline earths in
sufficient quantities into an acid leach circuit has the potential to result in unwanted
excess chemical reactivity, this situation will not occur from the processing of the
Uranium Material at the Mill. As described above, none of the alkaline earths will be
present as pure metals, or in the highest oxidation state (oxide) form. Hazards
associated with pure metals and oxides are not applicable and will not be discussed
further.
All other compound and complex forms of the alkaline earths anticipated in the Uranium
Material are compatible with either acid or alkaline leach solutions and any other process
chemicals to which they may be exposed in the Mill circuit. They will be precipitated as
sulfates or other insoluble salts, and discharged to the tailings. They do not pose any
incompatibility hazards in the Mill process.
Barium chloride was added to the raffinate solution to co-precipitate radium. The
average barium concentration in the feed is 4,150 mg/kg or ppm. The data from Cell 3
indicate that barium has historically been introduced into the Mill process, and the
assumption is that barium will also be present in the Cell 4A and 4B tailings. Barium
concentrations as high as 43,000 ppm have been processed at the Mill with no adverse
process effects, environmental impacts, or safety issues. Incompatible materials listed
for barium sulfate include phosphorous and aluminum. The barium will not be exposed
to these materials, and the addition of sulfuric acid at the Mill will not create any
additional worker safety or environmental hazards from contact with barium.
5.3.2 Transition Metals
Although in some circumstances, the introduction of oxides of the transition metals in
sufficient quantities into an acid leach circuit has the potential to result in unwanted
excess chemical reactivity, this situation will not occur from the processing of the
Uranium Material at the Mill. As described above, none of the transition metals will be
present as pure metals, or in the highest oxidation state (oxide) form. Hazards
associated with pure metals and oxides are not applicable and will not be discussed
further.
All other compound and complex forms of the transition metals anticipated in the
Uranium Material are compatible with either acid or alkaline leach solutions and any
other process chemicals to which they may be exposed in the Mill circuit. They will be
precipitated as sulfates or other insoluble salts, and discharged to the tailings. They do
not pose any incompatibility hazards in the Mill process.
5.3.3 Other Metals
Although in some circumstances, the introduction of oxides of the other metals in
sufficient quantities into an acid leach circuit has the potential to result in unwanted
excess chemical reactivity, this situation will not occur from the processing of the
Uranium Material at the Mill. As described above, none of the other metals will be
present as pure metals, or in the highest oxidation state (oxide) form. Hazards
associated with pure metals and oxides are not applicable and will not be discussed
further.
All other compound and complex forms of the other metals anticipated in the Uranium
Material are compatible with either acid or alkaline leach solutions and any other process
chemicals to which they may be exposed in the Mill circuit. They will be precipitated as
sulfates or other insoluble salts, and discharged to the tailings. They do not pose any
incompatibility hazards in the Mill process.
5.3.4 Metalloids
Although in some circumstances, the introduction of oxides of the metalloids in sufficient
quantities into an acid leach circuit has the potential to result in unwanted excess
chemical reactivity, this situation will not occur from the processing of the Uranium
Material at the Mill. As described above, none of the metalloids will be present as pure
metals, or in the highest oxidation state (oxide) form. Hazards associated with pure
metals and oxides are not applicable and will not be discussed further.
All other compound and complex forms of the metalloids anticipated in the Uranium
Material are compatible with either acid or alkaline leach solutions and any other process
chemicals to which they may be exposed in the Mill circuit. They will be precipitated as
sulfates or other insoluble salts, and discharged to the tailings. They do not pose any
incompatibility hazards in the Mill process.
5.3.5 Non-Metals
Nitrates have been introduced into the Mill's circuit with natural ores and alternate feeds
at levels as high as 350,000 mg/kg. Nffia.t9S-Wefe...Aot analy;:eG-in (:he dewatel:eG-sk:l6§e
~~-tRG-lJt.atlkJm-Material becauS<l tnoy .... 'ore not ant~
above trace levels. Nitrate plus nitrite as N was analyzed in one sample of dewatered
raffinate sludge in 2013 and was detected at 4,580 mg/kg. This level is well below the
level presenl in other alternate fe-eds regularlv processed at the Mill, such as the
Cameco Regen PI'oduct alternate feed material. Which contains concentrations rang ing
up to 350,000 mg/kg .The Mill has handled nitrate compounds in the Mill circuit and
tailings system with no adverse process, environmental, or safety issues.
Fluorides Aa\f.e...-l;)e-9fI-iffiFeduced il~to the Ml+I!s-G+f-GHi~itF1 R<"HUI:a1 Gros and alk;mate
feeds a110vels as l1igh ae 460,000 mg~was reported at 44 ,100 mq/kg in one sample of
dewatered raffinate sludge analyzed in 2013 This level is well below the levels
introduced into the Mill circuit with other alternate feeds already approved for processing
at the Mill. such as the Fansteel alternate feed material. which contained concentrations
of fluoride ranging up to 396,000 mg/kg. ~REles wore not analyzed ilT the dewatered
sludge ... ,hiGI'l Gomprisos the Uranium Material bocause they were n.04-a~~
present above trace levels. The Mill has handled fluoride compounds in the Mill circuit
and tailings system with no adverse process, environmental, or safety issues~
modifying the leach process as appropriate for the specific alternate feed.
Phosphorus. which will be Dresent in the phosphate form, was analyzed at 19,600 mg/kg
in tile dewatered sludge that comprises the Uranium material. This level is well within
the level present in other alternate feeds already approved for processing aL the Mill .
which have ranged uS high as 262.000 mg/kg of phosphorus in the phosphate form.
such as the Cameco Calcined Product alternate feed.
Am-mania was not a~d in the de-vvatefoEl--&ItJ.e§9----IHFHs/-t---Gem~fises-1-t=!-O-l:lfani·Hm
material bOGa~6e-J.t.-was-not-aRt-iG-F>a-t~e--f.*96Oflhrgeve trace levels. Anhydrous
ammonia gas or high concentrations of ammonium hydroxide solutions are incompatible
with strong oxidizers, halogen gases, acids, and salts of silver and zinc. If tfaee
quantities of ammonia are present, tRe-y-l!..wili not be present as anhydrous ammonia gas
or high concentration ammonium hydroxide and will not contact halogen gases at any
time in the Mill process. If traces of ammonia are present in the reactive form
faf'R-fA£}FH~r~~e-le-)--lt--wW-ee-at--eGRGG+ltJ:a.tiGAs too low-teAmmonla entering the leach
circuit would not be present in tho reactive hydroxide form . that is. ammonium Iwdroxide.
and will not be available to react with the silver and zinc already present in the Mill
tailings, or with the moderate oxidizer that may be added in the Mill acid leach circuit.
It should be noted that the Mill regularly handles 100% anhydrous ammonia which is
used to prepare concentrated ammonia solutions introduced into the yellowcake
precipitation area. The presence of ammonia in the process an d tailinqs is well within
the envelope of conditions normally encountered at the Mill and anticipated in th e
environmental assessments for the Mill's radioactive materials license.
5.3.6 Organic Compounds
As discussed in Section 4.1, no semi-volatile compounds were detected in the Uranium
Material. The levels of two volatile organic compounds detected were so near the
practical quantitation limits that their detection was most likely due to laboratory
influences, not presence in the Uranium Material.
6.0 Potential Worker Safety Issues
The Uranium Material is expected to have an average moisture content of approximately
55 percent, which will minimize the potential for dusting. If required, normal dust
controls, including central vents to a scrubber system utilized at the Mill can be
implemented to minimize any worker exposure to dusts from unloading operations. In
addition, normal operations in this area require the use of worker personal protective
equipment for prevention of dust inhalation and skin exposure; therefore, normal worker
protections already in place will be sufficient to prevent exposure to any additional metal
oxides, sulfates, or nitrates during processing of the Uranium Material.
The Mill manages hazards related to fluoride presence in alternate feed material by any
one or a combination of process variations includinq blending of bulk feed with
conventional ores, alkaline or carbonate leaching. or additional area monitoring in lhe
leach circuit and subsequent process steps. As discussed in Section 5.3.5 above. the
Mill has regularly managed alternate feeds with fluoride levels nearly an order of
magnitude higher than detected in the Uranium Material and has appropriate worker
protection SOPS. PPE an d monitoring programs 10 place for fluoride-bearing alternale
feeds.
7.0 Radiation Safety
The Uranium Material is derived from natural uranium ores, or through contact of surface
or groundwater with these ores. The Uranium Material contains the same radionuclides
as natural ores; however the concentrations of the isotopes vary somewhat from natural
ores. +A9 derived air GonGentFatieAS;-faCIia~ion proteotion meaSl:lfes, aAd omissions
oontrol meastl~e·F--arcs and att:ler-a~tafAate feods-at-tRe-Mil~F9--StIf.f.iGieAtly
~fOtectivo for-the PFaGeSSffl@ of tl=le-IJI:a-n.i~:H-"R-MataFial,
Based on the available data, all radlonuclides In the Uranium Material are present at
levels comparable to conventional ores or other alternate feeds previously processed, or
licensed for processing, at the Mill as discussed below.
Uranium is expected to have average urani um content from 0.95 to 1.23 percent.
Thesa levels are comparable to Arizona Strip ores, wl1ich contain averaqe uranium
levels from 0.40 to 1.0 percent. and well within those of other alternate feeds, such as
the Cameco UF4 material, which contained levels of uranium as high as 68.6 percent.
Thonum isotopes are expected to be present, per the RMPS. as follows:
• Th-228 449 to 1,110 pCi/g (weiahted averaae 699 pCi/g)
• Th-230 43.900 to 74.400 pCi/g (weighted average 55 ,685 pCi/g)
• Th-232 1.060 to 4.990 pCi/g (weiahted average 2.385 pCi/g)
Th-228 and Th-232 in the Uranium Material are within their respective levels identified in
W.R.Grace alternate feed. which eXhibited up to 3.222 pCl/q TI1-228 and 31.500 pCli g
Th-232. Th-230 in the Uranium Material is within the levels identified in Neva Test Site
alternate feed material which exhibited up to 2,300.000 pei/o Th-230.
Radium is expected to be present. per the RMPR, from 135 to 367 pCi/g (weighted
averaae 236 pCi/g). Ra-226 is well below the levels identified n other previously
approved alternate feed materials. such as the W.R. Grace alternate feed material which
exhibited up to 100400 pella Ra-226"
However. due to the elevated levels of !ll onum, EFRI has chosen to implement a sl)ecific
Standard Operating Procedure ("SOP") for the receipt. handling. storage, processing
and disposal of tailings from . the Uran ium Material. The SOP was developed tor. and
was approved by. U.S. NRC for use with other alternate feed materials with elevated
levels of the same radionuclides, such as previously-licensed alternate feeds Heritage
Minerals and W.R. Grace. A copy of the SOP is provided in Attachment 7 to the License
Amendment Application.
The primary hazards associated with elevated thorium, are associated with alpha
particulates (asSOcia ted with Th-230). and gamma emanation (from Th-228 and TI1-232),
which are both addressed by measures included in the high thorium SOP. The SOP
contains the following lypes of additional protections:
• Measures to minimize dusting and airborne transport of particulates from stored
alternate feed
• Measures to provide shielding. if required. for gamma emanation from stored
alternate feed
• Additional PPE
• Additional area and breathing zone monitoring
• Maintaining of resulting tailings under solution or soil cover. to minimize gamma
emanation and particulate disoersion
The protective measures identified in the attached SOP are designed to minimize
exposures to workers and the public via inhalation, ingestion. and dermal exposure.
EFRI anticipates thai the additional measures desfgl1sd to minimize exposure to
radionuclides through these routes will also be suitable for protection from exposure to
toxic metals through these routes.
The derived air concentrations, radiation protection measures. and emissions control
measures Llsed in the hiah thorium SOP are sufficiently protective for the processing o'f
the Uranium Material.
8.0 Potential Air Emissions Impacts
The introduction of a solid powder like the Uranium Material to any process may produce
two potential forms of air emissions: fugitive dusts, and/or hazardous gases.
Discussions in the previous sections demonstrate that engineering controls already in
place at the Mill will prevent the generation or dispersion of both of these types of
emissions. The Uranium Material will have a moisture content of approximately 55
percent, which will minimize dusting. In addition, the impurities will almost immediately
be converted to sulfates or other stable aqueous ionic forms, which are non-volatile and
produce no off gases.
Because the metals and ions in the Uranium Material are present at ppm levels, they are
not expected to generate a significant increase in load on the existing bag-house system
and air pollution control devices even if they reach the air control system as solids from
potential spills in the pre-leach area.
9.0 Potential Effects on Tailings System
9.1 Tailings Cell Uner Material Compatibility
The Uranium Material will be received as a moist solid filter cake from management of
aqueous pond materials at the Facility. A portion of this material may be insoluble in the
acid leach process at the Mill and therefore, the discharge sent to tailings may contain
some solid material ("sand"). The remainder of the Uranium Material will be soluble and
therefore be contained in the liquid phase after processing in the leach system. Tailings
from processing of the Uranium Material will be sent to one of two tailings cells at the
Mill, Cell 4A or Cell 4B or to a similarly designed new cell. The solutions from the
Uranium Material tailings will be recirculated through the Mill process for reuse. The
sands will be only a portion of the total mass of Uranium Material sent to the Mill from
the Site. However, assuming a worst case scenario that all of the solid material ends up
as sand in the tailings, it is estimated that for the main processing circuit, the additional
load to the tailings is minimal.
Cell 4A and 4B both have high-density polyethylene ("HOPE") liners. Cell 4A was
placed into service in October of 2008 and received conventional ore tailings sands and,
since July 2009, conventional ore tailings solutions. Cell 4B was authorized for use and
placed into service in February 2011, and has received conventional ore tailings
solutions. However, it can be assumed that over the life of these two tailings cells, each
will receive a comparable combination of tailings solutions and solids, from both
conventional ores and alternate feeds, as did tailings Cell 3. Hence, it is reasonable to
use known information on the composition of Cell 3, currently in the process of final
filling and closure, to represent the ultimate composition of either Cell 4A or 4B.
The constituents in the tailings sands and liquids resulting from the processing of
Uranium Materials are not expected to be significantly different from those resulting from
processing of conventional ores either in composition or in concentration of constituents.
Table 4 indicates that all of the constituents found in the Uranium Material have been
processed in the Mill's main circuit and/or the alternate feed circuit and are present in the
tailings system.
Except for the organic constituents, the constituents to be added to the Mill process are
similar to conventional ores. As discussed in Section 5.1.1 above. the two detected
organic constituents are assumed to be due to laboratory influences.
According to Gulec, et al. (2005), a study on the degradation of HOPE liners under acidic
conditions (synthetic acid mine drainage), HOPE was found to be chemically resistant to
solutions similar to the tailings solutions at the Mill. Mitchell (1985) studied the chemical
resistivity of PVC and HOPE at a pH range of 1.5 to 2.5 standard units using sulfuric
acid. This study concluded that PVC performed satisfactorily under these conditions and
HOPE performed better and was overall more stable under these acidic conditions.
As described above, it is expected that most of the metal and non-metal impurities
entering the leach system with the Uranium Material will be converted to sulfate ions,
precipitated, and eventually discharged to the tailings system.
Every metal and non-metal cation and anion component in the Uranium Material already
exists in the Mill's tailings system and/or is analyzed under the GW monitoring program.
A summary of the potential tailings composition before and after processing the Uranium
Material is presented in Table 4. Although tailings from the Uranium Material will be
placed in Cell 4A or 48, Table 4 is based on composition data from tailings Cell 3, which
has historically received both ores and alternate feeds.
Every component in the Uranium Material has been:
1. detected in analyses of the tailings cells liquids;
2. detected in analyses of tailings cells solids;
3. detected in analyses of alternate feed materials licensed for processing at the
Mill; or
L detected in process streams or intermediate products when previous alternate
feeds were processed at the Mill; ef;-
at concentrations that are generally comparable to or higher than the concentrations in
the Uranium Material.
As Gan be seen from Table 4 indicates the anticipated changes in metal and non-metal
constltue.nts In the taillnas following processing of he UraniUm Material. 'i none of the
~-Weffis..h:4f1e Ufafill:lffi-Mat.e-r.JaI-is-esfu"l:l.a.te-El-te-r~Fr-ent GOAGeA{-fa.Yon of the
t.aj»A~FROH3-t-~e-teAth-ef.-one-f}8fG9At, enEl
For some meta ls. ffi-some GaGes such as lithium. mercurv, or vanadium. due to their low
levels in the Uranium Material, the resulting concentration in tailings is expected to ~
aewndecrease. In all other cases. the concentration of metals will have increases
ranging from 0.3 percent to 144 percent. It should kept in mind that an increase of 152
percent ill thallium, for example, still represents an incremental increase of only 24 ppm.
and the Mill has previously processed and disposed tailings from al emates feed
containing twice that level.
The-Mill has already introduced tail ings from alternate feeds with sianificantly higher
levels of the non-metals. such as nitrate. phosphorous. and fluoride . than are present in
the Uranium Material. as discussed in Section 5.1! above. Although the uranium
Material may contain ammon ia al levels higher than in1roduced in other alternate feeds.
due to the Mill's use of ammonia in the precipitation circuit. the tailings system contc!ins,
and was designed for elevated concentrations of residual ammonia. As a result. due to
the appreciable concentration of ammonia al ready present in the tailings system , the
effect of the Uranium Material on the concentration in ammonia in tailings, an increase of
0.3 percent. is minimal.
The constituents in the Uranium Material, are expected to produce no incremental
additional environmental, health, or safety impacts in the Mill's tailings system beyond
those produced by the Mill's processing of natural ores or previously approved alternate
feeds. Since the impacts of all the impurities on the tailings system are already
anticipated for normal Mill operations, and permitted under the Mill's license, they have
not been re-addressed in this evaluation.
9.2 Groundwater Monitoring Program
One difference in the milling process of Uranium Material and disposal of tails in the
tailings cells at the Mill is the introduction of barium to the tailings system. The chemistry
of the tailings cells would limit the mobility of barium due to the abundance of sulfate in
the tailings cells. The insolubility of barium in the presence of sulfate is generally
consistent regardless of the liquid medium. That is, the solubility of barium sulfate in
cold water is 0.022 mg/L and in concentrated sulfuric acid is 0.025 mg/L (Handbook of
Chemistry and Physics, 68th Edition). At the listed concentrations of sulfate in the
tailings solutions (67,600 mg/L to 87,100 mg/L in Cell 4A or 29,000 to 190,000 mg/I in
Cell 3), a change in the barium concentration in the tailings solutions of 17 ppm (0.002
percent) would be negligible. Therefore, given the strong tendency of barium to partition
to solids, especially in the presence of sulfate, there is no reasonable potential for
barium to migrate to ground water from the tailings cells at the Mill in the unlikely event
of a leak in the tailings cells. Calcium Kd value in UDEQ Statement of Basis for the
Groundwater Discharge Permit (December 1, 2004) contains published Kd values for
calcium of 5 to 100 Ukg for sandy to clayey soils. The Kd for barium is 100 to 150,000
Ukg for the same soil types, indicating less mobility in groundwater. geAisGI1EFRI has
therefore concluded that barium is sufficiently represented by monitoring for calcium and
has identified no technical reason to add barium to the list of constituents monitored in
ground water in the vicinity of the tailings cells.
Excluding barium, chemical and radiological make-up of the Uranium Material is similar
to other ores and alternate feed materials processed at the Mill, and their resulting
tailings will have the chemical composition of typical uranium process tailings, for which
the Mill's tailings system was designed. As a result, the existing groundwater monitoring
program at the Mill will be adequate to detect any potential future impacts to
groundwater.
10.0 Conclusions and Recommendations
While elevated levels of certain constituents in the Uranium Material may be present, no
additional material management requirements during handling and processing will be
required. The Mill has successfully implemented proceSSing of previous alternate feeds
with similar or higher concentrations of each constituent contained in the Uranium
Material. For example, the Mill has successfully processed and recovered uranium from
uranium-bearing salts, calcium fluoride precipitates, recycled metals, metal oxides, and
calcified product, all of which posed potential chemical reactivity and material handling
issues comparable to or more significant than those associated with this Uranium
Material.
Based on the foregoing information, it can be concluded that:
1. All the constituents in the Uranium Material have either been reported to be, or
can be assumed to be, already present in the Mill tailings system or were
reported in other alternate feeds processed at the Mill, at levels generally
comparable to or higher than those reported in the Uranium Material.
2. All the constituents in the Uranium Material have either been reported to be, or
can be assumed to be, previously introduced into the Mill process, with no
adverse effects to the process, or worker health and safety.
3. All the known impurities in the Uranium Material have either been reported to be,
or can be assumed to be, previously introduced into the Mill tailings
impoundments, with no adverse effects to the tailings system, or human health
and safety.
LNe--The majority of constituent.§. in the Uranium Material will raise the respective
concentration in tailings mOFe than a fraction of a peFCeAta few tens 0 ppms an
the largest increases in concen tra tion will no more lhan few hundred ppms. Eh-Hn
some cases, the resulting concentrations of constituents in tailings will be
reduced.
4-:-5. Specific Mill procedures fo r processing of alternate feeds with elevated
thorium will be sufficiently protective of workers and the environment during the
processing of the Uranium Material.
·&.-6. There will be no significant incremental environmental impacts from the
processing of Uranium Material beyond those that are already anticipated in the
Environmental Impact Statements for the Mill.
~'r:7' .. ___ Spill response and control measures designed to minimize particulate
radionuclide hazards will be more than sufficient to manage chemical hazards
from the constituents of the Uranium Material.
11.0 References
• Austin, G.T. Shreve's Chemical Process Industries, Fifth Edition. McGraw Hill.
New York 1984.
• Center for Disease Control, Toxicity Profiles, accessed at
•
•
•
•
•
•
•
•
http://www.atsdr.cdc.govfToxProfiles on 9/12/11
Title 10 Code of Federal Regulations; Chapter I -Nuclear Regulatory
Commission, Part 40 -Domestic Licensing of Source Material: 40.4 -Definitions
(10 CFR 40.4)
Title 10 Code of Federal Regulations; Appendix A -Nuclear Regulatory
Commission, Part 40 -Domestic Licensing of Source Material: Criteria Relating
to the Operation of Uranium Mills and the Disposition of Tailings or Wastes
Produced by the Extraction or Concentration of Source Material From Ores
Processed Primarily for Their Source Material Content (10 CFR 40 Appendix A)
Title 40 Code of Federal Regulations; Protection of the Environment, Part 261 -
Identification and Listing of Hazardous Waste: Subpart A, 261.4 -Exclusions:
Subpart B -Criteria for Identifying the Characteristics of Hazardous Waste and
for Listing Hazardous Waste.
Gulec, S.8., C.H. Benson, and T. B. Edil, 2005. "Effect of Acid Mine Drainage on
the Mechanical and Hydraulic Properties of Three Geosynthetics", Journal of
Geotechnical and Geoenvironmental Engineering Vol. 131, No.8, ASCE, pp.
937-950.
Mitchell, D.H., 1985. "Geomembrane Compatibility Tests Using Uranium Acid
Leachate", Journal of Geotextiles and Geomembranes, Vol. 2, No.2, Elsevier
Publishing Co., pp. 111-128.
Notzl, H. Sequoyah Fuels Dewatered Tails Process Evaluation for Uranium
Recovery. October 8, 2004
US EPA Chemical Fact Sheets -accessed at www.epa.gov/chemfact on 10/6/10
Sax, N. Irvin~ and Lewis, Richard L. Sr. Hawley's Condensed Chemical
Dictionary, 11t Edition. Van Nostrand Reinhold. New York 1987.
Table 3: Incompatibilities and Chemical Hazards for Components of Uranium Material
Maximum Will constituent be present in this Will constituent be exposed to
Concentration chemical form? these incompatible agents?
Reported
(mg/kg in
Chemical dewatered sludge
Component Symbol unless noted) Incompatibilities
----
Aluminum AI 160,000 As AI20 3 -chlorine trifluoride, hot chlorinated No None present except acid.
rubber, acids, oxidizers
As AI -Strong oxidizers and acids, No None present except sulfuric acid
halogenated hydrocarbons
As pure powder -varies No --
As AI salts and alkyls -varies No. Aqueous solutions on Iy --
Ammonia NH4 2,880 mg/L in Strong oxidizers, halogens, acids, salts of No. Will only be present as None present except sulfuric acid.
dewatering filtrate silver and zinc ammonium salts in wet filter cake or
aqueous solution.
Antimony Sb 78.4 As metal and powder -strong oxidizers, No. None present except sulfuric acid.
acids, halogenated acids
Arsenic As As metal and inorganic compounds -strong Yes. As inorganic salts No. None present except moderate
I oxidizers, bromine azide oxidizers only, if used.
As organic compounds -varies No. ---
I
As AsH3 (arsine) -strong oxidizers, chlorine, No. No.
nitric acid
Barium Ba 4,150 As Barium oxides -reacts with water to form No .. No. Will already be in aqueous or wet
hydroxides; reacts with N204, hydroxylamines, filter cake form
S03, H2S
Beryllium Be 18.1 As BeQ -gives off toxic gases in fire No. --
Cadmium Cd <267 As CdO -reacts with magnesium, No. No.
decomposes on heating to form cadmium
fumes
Calcium Ca 114,000 As Ca oxides -react with water No. Will already be in aqueous or wet
filter cake form.
As Ca hydroxides -react with water No. Will already be in aqueous or wet
filter cake form.
As CaS04 -diazomethane, aluminum, Yes. None present except water. Will
phosphorous, water already be in aqueous or wet filter
cake form.
Table 3: Incompatibilities and Chemical Hazards for Components of Uranium Material
Maximum Will constituent be present in this Will constituent be exposed to
Concentration chemical form? these incompatible agents?
Reported
(mg/kg in
Chemical dewatered sludge
Component Symbol unless noted) Incompatibilities
-
As CaSi03 or CaOSi02 -none Yes --
Chromium Cr 605 As Cr02 -none No. -
As Cr03 -combustible materials (paper, No. No.
wood, silfur, aluminum, plastics)
Cobalt Co 133 As CoO -none No. .-
Copper Cu 2,360 As CuO -acetylene, zirconium No. No.
Fluoride F 23,118 in raw Varies with compound form. As inorganic Yes. '-
undewatered sludge salts -none
Iron Fe 1164,000 As Fe20 3 -calcium hypochlorite, carbon No. No.
monoxide, hydrogen peroxide
As Fe2(S04h -decomposes at high No. No.
temperature
As As2Fe206 -decomposes on heating to No. No.
yield fumes of arsenic and iron
Lead Pb 1,010 As PbO -strong oxidants, aluminum powder, No. No. None present except moderate
sodium; also decomposes on heating to form oxidizers only, if used.
lead fumes
Lithium Li <2.67 As LiH -strong oxidizers, halogenated No. No. None present except moderate
hydrocarbons, acids, water oxidizers only, if used.
Magnesium Mg 7,190 As MgC03 -acids, fonnaldehyde No. None present except sulfuric acid.
As MgO -chlorine, trifluoride, phosphorus No. No.
pentachloride
Manganese Mn 1,930 As Mn(OH)3 MN20 3, MnO -none No. --
Mercury Hg 1.41 As metal and inorganic compounds -Yes, but only as wet filter cake or No.
acetylene, ammonia, chlorine dioxide, azides, aqueous solution.
calcium, sodium carbide, lithium, rubidium,
copper
As organic compounds -strong oxidizers No. No.
such as chlorine gas
Molybdenum Mo 10,700 As metal -strong oxidizers No. No. Moderate oxidizers only, if used.
Table 3: Incompatibilities and Chemical Hazards for Components of Uranium Material
Maximum Will constituent be present in this Will constituent be exposed to I
Concentration chemical form? these incompatible agents?
Reported
(mg/kg in
Chemical dewatered sludge
Component Symbol unless noted) Incompatibilities
---
As soluble compounds -varies Yes. --
Nickel Ni 1,660 As NiO-iodine, H2S No. No.
Nitrates/Nitrites NOx 42,400 in raw None reported Yes. -
undewatered sludge
Phosphorus P 553 As phenylphosphine, phorate, phosdrin -No. -
none reported.
As phospine -air, oxidizers, chlorine, acids, No. -No. None present except sulfuric
moisture, halogenated hydrocarbons, copper. acid.
As phosphoric acid -strong caustics, most No. No.
metals.
As P4 -Air, oxidizers, sulfur, strong caustics, No. No.
halogens.
As phosphorus oxychloride -water, No. Will already be in wet filter cake or
combustible materials, carbon disulfide, aqueous form.
dimethyl formamide, metals (except nickel and
lead).
Potassium K 2,785 As KCN -strong oxidizers (such as acids, No. No.
acid salts, chlorates, and nitrates).
As KOH -acids, water, metals, halogenated No. No. None present except water and
hydrocarbons, maleic anhydride. Will not be sulfuric acid.
present in these forms.
Selenium Se 348 As SeO -none No. --
Silver Ag 90.8 As Ag20 -fire and explosion hazard with No. No. Will not be exposed to ammonia
organic material or ammonia in circuit.
Sodium Na 7,480 As Na2AIF6 -strong oxidizers No. No. Moderate oxidizers only, if used
As NaN3 -acids, metals, water No. No. None present except sulfuric
acid.
As Sodium bisulfate (dry product) -heat No. Will only be present in wet filter No.
cake or aqueous solution.
As NaCN -strong oxidizers (such as acids, No. No.
Table 3: Incompatibilities and Chemical Hazards for Components of Uranium Material
Maximum Will constituent be present in this Will constituent be exposed to
Concentration chemical form? these incompatible agents?
Reported
(mglkg in
Chemical dewatered sludge
Component Symbol unless noted) Incompatibilities
acid salts, chlorates, nitrates)
As NaF -strong oxidizers No. No.
As Sodium fluoroacetate -none reported No. --
As NaOH -water, acids, flammable liquids, No. No. None present except sulfuric
organic halogens, aluminum, tin, zinc, acid.
nitromethane
As sodium metabisulfite -heat No. --
Strontium Sr 1,210 None reported Yes. --
Thallium TI 5,860 Varies with compound Will only be present in wet filter cake --
or aqueous solution.
Vanadium V <1 .60 As dust or fume -lithium, chlorine trifluoride No. Will only be present in wet filter No.
cake or aqueous solution.
Zinc Zn <751 As ZnO -none No. -
Note: None of the above incompatibilities are applicable to the components as they will be present in the SFC Uranium Material. None of the components will
be present in pure/reduced metal form or as pure metal oxides. None of the fluoridated, sulfite, or cyanide, compound or hydroxylated (caustic forms) of the
alkali metals or alkaline earths are expected to be present. None of the components will be exposed to any of the incompatible agents identified in the table.
All of the components are expected to be present in inert hydrated, nitrated, or other soluble salt forms, compatible with the aqueous solutions in the Mill's acid
digestion and feed circuit.
Table 4 Comparison of Uranium Material to Tailings and Alternate Feeds
G H Difference f
A C D F Conc. in Mill between Column G Increase in Mill
Estimated B Cone. Range in Estimated Average E Mass in Mill Tailings after and 0 (Incremental Tailings Cone.
Average Cone. Estimated Mill Tailings before Cone. in Mill Tailings Estimated Tailings after Uranium Increase in Mill Tailings after Uranium J
in Uranium Mass in Processing before Processing Current Mass in Uranium Material Material Conc. after Uranium Material Cone. in Ores and Other
Material (mg/kg Uranium Uranium Material Uranium Material Mill Tailings Processing Processing Material Processing) Processing Alternate Feed Materials
IComponent oroom)" Material (tond (mg/L or ppm )3A (mg/L or ppm)3B, 3C (tons)4 (tons)5 (ppm)6 (ppm)7 1%}8 (mg/L or ppm)9"O, 11
IAmmonla as N 5210 3918 3-13.900 3.131 5_639 5.678.1 ~:.I-1O 8.6 0 " 100-730
!AlumInum (AI) 160.000 1.203.20 330-2.530 3.154 5,680 6.883.6 3.806 652.2 20.7 2,000-133.000
Anlimonv (Sb)" 78.4 0.59 <20 20 36 36.6 20 0.2 1.2 0.01-120
Arsenio (As) 3.030 22-19 0.3-440 149 269 291.3 161 12.0 8.0 3.5-16.130'
Barium (Ba) , 4,150 31 .2.1 0.021-0.1 28 50 81.6 45 17.1 61;:: 21-43.000 I
BelYlIium (Be) l e.7 0.14 0.347-0.78 1.00 2. 1.9 1 0,1 7.4 1-105
Cadmium (Cd) 267 2_01 1.64-6.6 1.0 2 3.8 2-1.1 110.6 M04-59.ooo i
Calcium (Ca) 114.000 857.28 90-630 1.052 1,895 2.751.9 1,522 469.6 44.6 up to 217.000 I
Cobalt (Co) 133 1.00 14-120 83.0 149 150.5 83 0.2 0.3 9-350,400
Chromium (Gr) , 605 4.55 1.0-13 24.0 43 47.8 26 2,4 10.1 8>16,.000 I
Cc:lpjW (eu) 2,360 17.75 2.110-B.000 230 415 432.4 239 8.9 3.8 8-296.000
Fluoride 44.100 331.63 0,02-4.440 1.695 3.053 3.3843 1.871 176.3 10.4 3-460.000
Iron (Fe) 164:;000 1,233.28 1 ,080-3.400 2.608 4.697 5,930.3 3.27-9 671-1 25.7 up to 54,000
Lithillm (Li) 2.67 0.02 1.080-3.401 17.2 31 31 .0 17 -0.1 -0.4 upt0810
Lead (Pb) 1.010 7.60 0-21 -6.0 4 7 14.8 8 4.2 104.6 9-2.36,000
MaQn~ium (M(1l 7,190 54.07 1.800-7,900 4.938.00 8.893 8.947.4 4,947 9.4 0.2 1.020-43,400
Manganese (Mnl 1930 14.51 74-222 444 800 814.2 450 62 1.4 172-3,070
Mercu!\l (HQ) 1.41 0.01 0.0008-17.6 3.0 5 5.4 3 0.0 -02 0.0004-14
Molvtidenum (MQ)_ 10,TOO 80.46 0.44-240 143.0 258 338.0 187 43_9 30.7 12-17.000
NTCkal [NI) 12 1,660 12.48 7.2-370 87 157 169.2 94 6.5 7.5 7-450.000
Nitrate + Nitrite as N 4.580 34.44 24.00 24 43 777 43 189 78.9 0.6-350.000
Phosphorus (P) 19.600 147.39 88.1 -620 90.1 162 309.7 171 81.1 90.0 11.900-86.500
Potassir)m (1<) 7:740 58.2.0 219-826 458.0 825 883.1 488 30.3 6.6 17·1.440
Selenium (Se) 348 2.62 0.18-2.4 1.0 2 4.4 2 1.4 144.3 0.02-710
Sliver (Aq) 90.8 0.68 0.005-0.14 1.0 2 2.5 1 0.4 373 0.007-80
SodIum (Na) 7,480 56.25 1.400-10.000 5.828 10.496 10.552.5 5.835 6.9 0.1 UP to 28.800
Detected in tailings. so known
to originate with ores or other
Strontium (Sr) 1.210 9.10 28.900-190.000 7 12. 21 .5 12 5_0 72.8 alternate feeds_
Thallium (TI) 5,860 44,07 0.7-45 16 29 72.9 40 24.3 151.9 0.02-960
Vanadium IVl 1.6 0.01 136-510 264 475 475.5 263 -1.1 -0.4 10-25,000
Zinc: (Zn) 751 5.65 50-1.300 637 1.147 1.152.9 637 0.5 0.1 8-14.500 _.--
Table 4 Comparison of Uranium Material to Tailings and Alternate Feeds
Notes to Table 4:
1. The concentration in the Uranium Material is based on Section D.1. of the RMPR. Ranges were not provided. Values reported as less than «) were used as reported.
2. Estimated mass in the Uranium Material is calculated by multiplying column B by an assumed 7,520 dry tons of Uranium Material.
3A & 3B. Mill tailings range and average concentrations were taken from Mill tailings samples to date, as summarized in Table 5 of the draft Statement of Basis ("SOB") for the Utah
Groundwater Discharge Permit ("GWDP") for the Mill (November 29,2004).
A. All constituents in Uranium Material have been analyzed in Mill tailings. Table 5 of SOB and Column C, above, summarize range of measured values.
Values reported as less than ("<") were used as whole values.
B. Column D is theoretical average from Cell 3 plus processing of Fansteel alternate feed. Copper, lithium, and strontium were not present
in FMRI alternate feed and were not adjusted from GWDP SOB Table 5 in Column D.
C. Phosphate (P04=) reported in FMRI was adjusted to phosphorus (P) for consistency with SOB Table 5
4. Estimated current mass in Mill tailings Cell 3 is 1,801,000 dry tons.
5. Mass in Mill tailings after Uranium Material processing is calculated by adding columns Band E.
6. The concentration in Mill tailings after Uranium Material processing is calculated by dividing column F by 1,808,520, being the existing volume of tailings in
Cell No 3 of 1,801,000 dry tons plus the assumed 7,520 dry tons of Uranium Material.
7. The increase in Mill tailings concentration after Uranium Material processing (ppm) shows the increase (decrease) in concentration of each constituent in the
Mill's tailings, stated in ppm of the total mass of tailings in Cell No.3, which is calculated as the difference between column G and column D.
8. The increase in Mill tailings concentration after Uranium Material processing is the ratio of Column D to Column H expressed in %
9. The concentration in other alternate feeds represents some selected concentrations for constituents found in characterization data for other alternate feed
materials licensed for processing at the Mill, for comparison purposes.
10. Phosphorus value approximated from reported phosphate values times 0.33. Actual value will be higher if phosphorus is present in forms other than phosphate.
11. Sodium and lithium values are wet basis from Maywood alternate feed. Dry basis value would be higher.
12. Column D includes constituents added via FMAI processing. As, Sa, Cr, Ni, and Sb were not analyzed for in FMAI ponds but were detected in perimeter soils present
and assumed to be in ponds as well.
• Results are reported on a dry weight basis.
ATTACHMENT 6
Cross Index to ORC Interrogatory Template for Review of License Amendment
Requests and Environmental Reports under UAC R313-24
DRC Interrogatory Where Addressed in This
Number Topic Regulatory Basis Document Where Addressed in Other Documents
Environmental Analysis -Radiological and Section 1.0-1.4, 2.3, 2.5, 4.1,
UAC R313-24-3-01AlOl Nonradiological impacts UAC R313-24-3 Attachment 5 ER Lic. App 3.1-3.10; ER Ce1l4B 9.0
ER Lie. App. 3.4.1-3.4.4,. 3.5; Rec PI~n 1.6; ER
Geology and Soils (Land) RG 3.8, Section 6.1.4.1 Section 4.1 Ce1l4B 6.0
ER Lie. App. 3.13.2.2, Figure 3.13-1 ; Dames
Exposure Pathways RG 3.8, Section 5.2.1 Section 4.1 and Moore 5.2; ER Ce1l4B 10.1
Liquid Effluents RG 3.8, Section 5.2.2 Section 4.1,4.6,4.8 Rec. Plan 2.2.3.2; Dames and Moore 5.2
GW Permit App. 2.6: Dames and Moore 2.7.4,
Airborne Effluents RG 3.8, Section 5.2.3 Section 4.1, 4.8 Dames and Moore 5.2
Direct Radiation RG 3.8, Section 5.2.4 Section 2.3, 4.1, 4.9, 4.10 Dames and Moore 2.7.4
Effects of Sanitary and Other Waste
Discharges RG 3.8, Section 5.4 Section 4.1 Dames and Moore 5.4
Other Effects RG 3.8, Section 5.5 Section 4.1, 4.2.2 Dames and Moore 5.5
NUREG-1620, Section
Hazard Assessment 4.3.3.1 Section 4.1, Attachment 4 GW Permit App. 2.6-2.7
NUREG-1620, Section
Exposure Assessment 4.3.3.2 Section 4.1 GW Permit App. 2.6-2.7
Accidents DG-3024, Section 6 Section 4.1, 4.2.3 ER Lic. App. 4.0
Mill Accidents Involving Radioactivity RG 3.8, Section 7.1 Section 4.1,4.4.1 ER Lic. App. 4.0
Other Accidents RG 3.8, Section 7.3 Section 4.1, 4.2.3 ER Lic. App. 4.0
Summary of Annual Radiation Doses RG 3.8, Section 5.2.5 Section 4.1 ER Lie. App Tables 3.13-3, 3.13-4
Environmental Analysis -Impact on
UAC R313-24-3-0lB/Ol Waterways and Groundwater UAC R313-24-3 Section 4.1,4.6,4.7 GW Permit App. 2.5-2.7 ; ER Cell 4B 10.0
ER Lie. App. 3.7.1.1-3.7.1.3; Rec Plan 1.4.1-
Surface Water RG 3.8, Section 6.1.1 Section 4.1, 4.7 1.4.3, 1.7.5.5
Physical and Chemical Parameters (Ground
I Water) RG 3.8, Section 6.1.2.2 Section 4.1, 4.6, Attachment 4 GWDP Table2
UAC R313-24-3-01C/Ol Environmental Analysis -Alternatives UAC R313-24-3 Section 4.1, 4.14 ER Lic. App. 2.0-2.4 I
Alternatives to the Proposed Action RG 3.8, Section 10 Section 4.1, 4.14 ER Lie. App 2.1 , 2.4 I
Benefit -Cost Analysis RG 3.8, Section 11 Section 4.1, 4.13 ER Lie. App. 5.0; Rec Plan Attachment C
UAC R313-24-3-0lD/Ol Environmental Analysis -Long-Term Impacts UAC R313-24-3 Section 4.1, 4.5.3, 4.11 ER Lic. App. 5.0; ER Ce1l4B 14.0
Mill Decommissioning DG-3024, Section 8.1 Section 4.1, 4.5.3 Rec. Plan 3.2.3,
Site and Tailings Reclamation DG-3024, Section 8.2 Section 4.1, 4.5.3 Rec. Plan 3.2.1,3.2.2.;
Decommissioning and Reclamation RG 3.8, Section 9 Section 4.1,4.5.3 Rec. Plan Attachment A, 3.2.1,3.2.2 ---
DRC Interrogatory Where Addressed in This
Number Topic Regulatory Basis Document Where Addressed in Other Documents
Decommjssioning Plan for Land and NUREG-1620, Section
Structures 5.2.3 Section 4.1, 4.5.3 Rec. Plan 3.2.1
Satistied by ongoing compliance with mill
10CFR40.26(c)(2)-02/01 General License UAC R313-24-4 license
Satisfied by ongoing compliance with mill
10CFR40.31 (H)-03/01 Application for Specific Licenses UAC R313-24-4 license
Corporate Organization and Administrative Satisfied by ongoing compliance with mill
Procedures DG-3024, Section 5.1 Section 4.1, Section 4.12 license
Satisfied by ongoing compliance with mill
Management Control Program DG-3024, Section 5.2 Section 4.1, Section 4.12 license
Satistied by ongoing compliance with mill
Management Audit and Inspection Program DG-3024, Section 5.3 Section 4.1, Section 4.12 license
Satisfied by ongoing compliance with mill
Qualifications DG-3024, Section 504 Section 4.1, Section 4.12 license
Satisfied by ongoing compliance with mill
Training DG-3024, Section 5.5 Section 4.1, 4.4, 4.10.2, 4.12 license
Satisfied by ongoing compliance with mill
Security DG-3024, Section 5.6 Section 4.1,4.12 license
Satisfied by ongoing compliance with mill
Quality Assurance DG-3024, Section 7 Section 4.1 license
Satisfied by ongoing compliance with mill
References DG-3024 Section 4.1 license
Satisfied by ongoing compliance with mill
1 OCFR40.4( c )-04/01 Terms and Conditions of Licenses UAC R313-24-4 Section 4.1 license
10CFR40.40.42(K)(3)(I)-Sacisfied by ongoing compUance with mill
05/01 Expiration, Termination, Decommissioning UAC R313-24-4 Section 4.1 license
Satisfied by ongoing compliance with mill
10CFR40.61-06/01 Records UAC R313-24-4 license
10CFR40.65(A)(I)-07/01 Effluent Monitoring Reporting Requirements UAC R313-24-4 Section 4.1 Rec. Plan 1.7.5.4
Mill Effluent Monitori ng (Proposed
Operational Monitoring Program RG 3.8, Section 6.2.1.1 Section 4.1 Rec. Plan 1.7.5.4
Enviromental Radiological Monitoring
(Proposed Operational Monitoring Program) RG 3.8, Section 6.2.1.2 Section 4.1 Rec Plan 2.3.2.19 (c), (d); ER Cell4B lOA
Meteorological Moniloring (Proposed Rec. Plan 1.1.1-1.1.3, 2.3.2.1(d), 1.7.5.6; ER
Operalional Monitoring Program) RG 3.8, Section 6.2.3 Section 4.1 Ce1l4B 2.2
IOCFR40.INTRODUCTIO Capacity of Tailings or Waste Systems Over
N-08/01 the Lifetime of Mill Operations UAC R313-24-4 Section 4.1, 4.5.2 GW Permit App. 2.15.2.3
DRC Interrogatory Where Addressed in This
Number Topic Regulatory Basis Document Where Addressed in Other Documents
10CFR40APPENDIX A,
Introduction-09/01 Alternative Requirements UAC R313-24-4 Section 4.1 ER Lic. App 2.1 -2.4
10CFR40 APPENDIX A, Permanent Isolation Without Ongoing
CRITERION 1-10/01 Maintenance UAC R3 1 3-24-4 Section 4.1 ,4.5.3 Rec Plan 3.2.3.1
NUREG-1620, Section
Slope Stability 2.2.3 Section 4.1, 4.5.3 Rec Plan 3.3.6
NUREG-1620, Section
Settlement 2.3.3 Section 4.1, 4.5.3 Rec Plan 3.3.6
NUREG-1620, Section
Liquidifacation Potential 2.4.3 Section 4.1,4.5.3 Rec Plan 3.3.6
10CFR40, APPENDIX A,
CRITERION 2-11/01 Proliferation UAC R313-24-4 Section 4.1 Rec Plan 3.3.6
lOCFR40, APPENDIX A,
CRITERION 3-12/01 Placement Below Grade UAC R313-24-4 Section 4.1 OW Permit App. 2.5.1.5
10CFR40. APPENDIX A,
CRITERION 4-13/01 Location and Design Requirements UAC R313-24-4 Section 4.1 Rec. Plan 3.1
Site Location and Layout RG 3.8, Section 2.1 Section 4.1 Rec Plan 1.1, Figure 3.2-1; ER Lic. App 3.2
Site Area RG 3.8 Section 3.1 Section 4.1 Rec Plan 1.1, Figure 1-2, Figure 3.2-1
Geography DG-3024, Section 2.1.1 Section 4.1 Rec Plan 1.1-1.3
Land Use and Demographic Surveys (Land) RG 3.8, Section 6.1.4.2 Section 4.1 FES 2.5; ER Cell 4B 3.0 I
Uses of Adjacent Lands and Waters RG 3.8, Section 2.2 Section 4.1 FES 2.5; ER Cell 4B 3.0
ER Lic. App. Figure 3.9-1 ; FES 2.4.1.2; ER Cell
Population Distribution RG 3.8, Section 2.3 Section 4.1 4B 4.0
Demography DG-3024, Section 2.1.2 Section 4.1 FES 2.4.1.2, 2.4.1 .3, 2.4.2
Meteorology RG 3.8, Section 2.8 Section 4.1 Rec Plan 1.1, 1.7.5.6; ER Ce1l4B 2.0
DG-3024, Section 2.2 Section 4.1 Rec Plan 1.1, 1.7.5.6; ER Ce1l 4B 2.0
RG 3.8, Section 6.1.3.1 Section 4.1 Rec Plan 1.1, 1.7.5.6; ER Ce1l 4B 2.0
Models (Air) RG 3.8, Section 6.1.3.2 Section 4.1 ER Lic App. 3.3.2
Geology and Soils RG 3.8, Section 2.5 Section 4.1 Rec Plan 1.6
DG-3204, Section 2.4.1 Section 4.1 Rec Plan 1.6
Seismology RG 3.8, Section 2.6 Section 4.1 Rec Plan 1.6.2.4, 1.6.2.5
DG-3024, Section 2.4.2 Section 4.1 Rec Plan 1.6.3, 1.6.3.1, 1.6.3.2
NUREG-1620, Section RecPlan 1.5.1.2, 1.5 .1.3, Figure 1.5-1 , 1.5-3;
Hydrological Description of Site 3.1.3 Section 4.1 ER Cell 4B Appendix A
Surface Water (Hydrology) RG 3.8, Section 2.7.2 Section 4.1 GWDP LF.IO
---._-
DRC Interrogatory Where Addressed in This
Number Topic Regulatory Basis Document Where Addressed in Other Documents
DG-3024, Section 2.3.2 Section 4.1 GWDP LF.W
NUREG-1620, Section
Flooding Determinations 3.2.3 Section 4.1 GW Permit App. 2.13
Surface Water Profiles, Channel Velocities, NOREG-1620, Section
and Shear Stresses 3.3.3 Section 4.1 GW Permit App. 2.4 I
Ground Water (Hydrology) RG 3.8 Section 2.7.1 Section 4.1 Rec Plan 1.5.1.2, 1.5.1.3, Figure 1.5-1 , 1.5-3
DO-3024, Section 2.3.1 Section 4.1 Rec Plan 1.5.1.2, 1.5.1.3, Figure 1.5-1, 1.5-3
Radiological Surveys RG 3.8, Section 6.1 Section 4.1 ER Cell4B 10.3-10.4
NUREG-1620, Section Section 4.1, 4.5.1, Attachment
Site and Uranium Mill Tailings Characteristics 2.1.3 5 Rec. Plan 2.2 I
NUREG-1620, Section '
Disposal Cell Cover Engineering Design 2.5.3 Section 4.5.3 GW Permit App. 2.7.2.4; Rec Plan 3.2.2.1
NUREG-1620, Section
Design of Erosion Protection Covers 3.5.3 Section 4.5.3 GW Permit App. 2.7.2.4; Rec Plan 3.2.2.1, 3.3.5
UAC R3 I 3-24-4,
10CFR40, APPENDIX A, NUREG-1620 section
CRITERION SA(I)-14/01 Groundwater Protection Standards 4.2.3 Section 4.1, 4.6 GWDP LA Table I, LB, LC Table 2, I.E
CRITERION SA(2)-IS/01 Liner UAC R313-24-4 Section 4.1, 4.6 GWDP 1.0.2, I.E.8 (c), I.E.7(f)
10CFR40, APPENDIX A, Exemption from Groundwater Protection
CRITERION SA(3)-16/01 Standards UAC R313-24-4 Section 4.6 Rec. Plan 2.3 .1.1 (a)
10CFR, APPENDIX A,
CRITERION SA(4)-17/01 Prevent Overtopping UAC R313-24-4 Section 4.1 Rec Plan 2.2.3.1,2.2.3.2
10CFR APPENDIX A,
CRITERION SA(S)-18/01 Dikes UAC R313-24-4 Section 4.1 Rec Plan 2.2.3.1, 2.2.3.2
10CFR APPENDIX A, Cover and Closure at End of Milling
CRITERION 6(1)-19101 Operations UAC R313-24-4 Section 4.1, 4.5.3 GW Permit App. 2.19
NUREO -1620, Section
10CFR40, APPENDIX A,
Radon Attenuation 5.l.3.1 Section 4.1,4.5.3 OW Permit App. 2.19; Rec Plan 3.3.2
NUREG-1620, Section
Gamma Attenuation 5.1.3.2 Section 4.1,4.5.3 GW Permit App. 2.19; Rec Plan 3.3.2
NUREG-1620, Section GW Permil App. 2.19; Rec Plan 3.3.6.3.3.8: ER
Cover Radioactivity Content 5.1.3 .3 Section 4.1 ,4.5 .3 Cell4B Figure 13
CRITERION 6(2)-20/01 Verify Effectiveness of Final Radon Barrier UAC R313-24-4 Section 4.1,4.5.3 Rec Plan. 3.2, 3.2.3.1 ; GW Permit App. 2.19.4
10CFR40, APPENDIX A,
CRITERION 6(3)-21101 Phased Emplacement of Final Radon Barrier ~AC R313-24£ _ Section 4.5.3 _ Rec Plan. 3.2, 3.2.3.1 ~~R Ce1l4B Table 5 __
DRC Interrogatory Where Addressed in This
Number Topic Regulatory Basis Document Where Addressed in Other Documents ,
10CFR40, APPENDIX A, Elevated Raduim Concentrations in cover
I CRITERION 6(5)-23/01 Materials UAC R313-24-4 Section 4.5.3 GW Permit App. 2.19; Rec Plan 3.3.6, 3.3.8
NUREG-1620, Section GW Pcnilll App_ 2.19; Rec Plan 3.3.6.3.3.8: ER'
Cover Radioactivity Content 5.1.3.3 Section 4.1,4.5.3 Cell4B Figure 13
10CFR40, APPENDIX A, Concentrations of Radionuclides other than I
CRITERION 6(6)-24/01 Radium in Soil UAC R313-24-4 Section 4.5.3 GW Permit App. 2.19; Rec Plan 3.3.5
Background Radiological Characteristics RG 3.8, Section 2.1 Section 4.1 Lic. App. 3.13.1; ER Cell 4B 9.0
10CFR40, APPENDIX A,
CRITERION 6(7)-25/01 Nonradiological Hazards UAC R313-24-4 Attachment 5 Dames and Moore 3.3.1; ER Ce1l4B 9.0 I
Regional Nonradiological Characteristics RG 3.8, Section 2.11 Section 4.1 Dames and Moore 3.3.1; ER Cell 4B 9.0
Concentrations of Nonradiocative Wastes RG 3.8, Section 5.3 Section 4.5.1, Attachment 5 Dames and Moore 3.3.1; ER Cell4B 9.0
10CFR40, APPENDIX A,
CRITERION 6A(I)-26/01 Completion of Final Radon Barrier UAC R313-24-4 Section 4.5.3 Rec Plan. 3.2, 3.2.3.1; GW Permit App. 2.19.4
10CFR40, APPENDIX A,
CRITERION 6A(2)-27/0l Extending Time for Milestones Performance UAC R313-24-4 Section 4.5.3 Rec Plan. 3.2, 3.2.3.1; GW Permit App. 2.19.4
10CFR40, APPENDIX A, Accepting Uranium Byproduct Material from
CRITERION 6A(3)-28/01 Other Sources During Closure UAC R313-24-4 Section 4.5.3 License Condition 9.11
lOCFR40, APPENDIX A, Preoperational and Operational Monitoring
CRITERION 7-29/01 Programs UAC R313-24-4 Section 4.1 Rec Plan 2.3.2
10CFR40, APPENDIX A,
CRITERION 8-30/01 Effluent Control During Operations UAC R313-24-4 Section 4.1 GW Permit App. 2.15
Gaseous and Airbourne Particulate Materials DG-3024, Section 4.1 Section 4.1 GW Permit App. 2.15
Liquids and Solids DG-3024, Section 4.2 Section 4.1 GW Permit App. 2.15
Contaminated Equipment DG-3024, Section 4.3 Section 4.1 OW Permit App. 2.15
Sources of Mill Wastes and Effluents RG 3.8, Section 3.4 Section 4.4 GW Permit App. 2.15; Dames and Moore 3.3
Control of Mill Wastes and Effluents RG 3.8, Section 3.5 Section 4.4 GW Permit App. 2.15; Dames and Moore 3.4
Sanitary and Other Mill Waste Systems RG 3.8 Section 3.6 Section 4.1 GW Permit App. 2.15; Dames and Moore 3.5
Effluents in the Environment RG 3.8, Section 5.1.2 Section 4.1 GW Permit App. 2.15; Dames and Moore 3.3
Effluent Control Techniques DG-3024, Section 5.7.1 Section 4.1 GW Permit App. 2.15; Dames and Moore 3.3
External Radiation Exposure Monitoring
Program DG-3024, Section 5.7.2 Section 4.1 GW Permit App. 2.15
Airborne Radiation Monitoring Program DG-3024, Section 5.7.3 Section 4.1 GW Permit App. 2.15; ER Lie. App 3.3.2
Exposure Calculations DG-3024, Section 5.7.4 Section 4.1 Rec. Plan Attachment F
DRC Interrogatory Where Addressed in This
Number Topic Regulatory Basis Document Where Addressed in Other Documents
Bioassay Program DG-3024, Section 5.7.5 Section 4.1 Rec Plan 3.2
Contamination Control Program DG-3024, Section 5.7.6 Section 4.1 Rec Plan 3.2
Airborne Effluent and Environmental GW Permit App. 2.9; Rec Plan 2.3; Dames and
Monitoring Programs DG-3024, Section 5.7.7 Section 4.1 Moore 3.3; ER Cell 4B Appendix C
Groundwater and Surface Water Monitoring GWDP I.E, IF; Rec Plan 2.3.1.1; ER Cell 4B
Programs DG-3024, Section 5.7.8 Section 4.1 10.2
Control of Windblown Tailings and Ore DG-3024, Section 5.7.9 Section 4.1 Rec Plan 3.2.3.1
10CFR40, APPENDIX A,
CRITERION SA-31/01 Daily Inspections UAC R313-24-4 Section 4.1 Rec Plan 2.3.2.2(a)
10CFR40, APPENDIX A,
CRITERION 9-32/01 Financial Surety Arrangements UAC R313-24-4 Section 4.5.3 Surety 2010
Financial Assurance DG-3024, Section 8.3 Section 4.5.3 Surety 2010
NUREG-1620, Section
Isurety 2010 Maintaining Financial Surety 4.4.3(10) Section 4.5.3
10CFR40, APPENDIX A,
CRITERION 10-33/01 Costs of Long-Term Surveillance UAC R313-24-4 Section 4.5.3 Surety 2010
Duty to Apply for a Groundwater Discharge
UAC R317-6-6.1-34/01 Permit UAC R313-24-4 Section 4.1, 4.6 GWDPIV.D
UAC R317-6-6.3-35/01 Groundwater Discharge Permit Application UAC R313-24-4 Section 4.1, 4.6 GWDPIV
UAC R317-6.6.4-36/01 Issuance of Discharge Permit UAC R313-24-4 Section 4.1, 4.6 GWDPIV
UAC R317-6-6.9-37/01 Permit Compliance Monitoring UAC R313-24-4 Section 4.1, 4.6 GWDPHI I
Examination of Compliance and Monitoring NUREG -1620, Section I
I Program 4.3.3.4 Section 4.1, 4.6 GWDP I.P.I I
UAC R317-6-6.10-38/01 Background Water Quality Determination UAC R313-24-4 Section 4.1, 4.6 GWDP I.B; ER Lic App. 3.7.3.2 (c) I
Commencement and Discontinuance of
UAC R317-6-6.10-39/01 Groundwater Discharge Operations UAC R313-24-4 Section 4.6 GW Permit App. 2.19
UAC R317-6-6.12-40/01 Submission of Data UAC R313-24-4 Section 4.6 GWDP I.P.1
Reporting of Mechanical Problems or
UAC R317-6-6.13-41/01 Discharge System Failures UAC R313-24-4 Section 4.6 GWDP I.G; GW Permit App 2.15
UAC R317-6-6.10-42/01 Correction of Adverse Effects UAC R313-24-4 Section 4.6 GWDPI.G
NUREG-1620, Section
Corrective Action Assessment 4.3.3.3 Section 4.6 GWDP LG
UAC R317-6-6.10-43/01 Out-of-Compliance Status UAC R313-24-4 Section 4.6 GWDPI.G
Procedure When a Facility is Out-of-
UAC R317-6-6.10-44/01 Compliance UAC R313-24-4 Section 4.6 GWDPLH
DRC Interrogatory Where Addressed in This
Number Topic Regulatory Basis Document
UAC R317-6-6.10-4S/01 Groundwater Discharge Permit Transfer UAC R313-24-4 Section 4.6
Notes:
If not stated otherwise, section number refers to section in the license amendment application, not its attachments.
References:
GWDP -"Ground Water Discharge Permit UGW370004". July 14,2011
ER Cell4B -"Environmental Report in Support of Construction Tailings Ce1l4B".
Revised and Resubmitted September 11, 2009
GW Permit App. -"Permit Renewable Application. State of Utah Ground Water
Discharge Permit NO. UGW370004". September 1,2009
Rec. Plan -"Reclamation Plan White Mesa Mill Blanding, Utah. Radioactive Material
License NO. UT1900479 Revision 4.0". November 2009
ER Lic. App. -"White Mesa Uranium Mill License Renewal Application. State of Utah
Radioactive Materials License No. UT1900479". Volume 4 of 5 (Environmental Report).
February 28, 2007
Dames and Moore -"Environmental Report. White Mesa Uranium Project. San Juan
County, Utahfor Energy Fuels Nuclear, Inc". Prepared by Dames and Moore. January 30,
1978
FES -"Final Environmental Statement related to operation of White Mesa Uranium
Project. Energy Fuels Nuclear, Inc". May 1979.
Surety 2010 -"Revised Cost Estimatesfor Reclamation of the White Mesa Mill and
Tailings Management System". November 23 20lO.
License Condition -"Utah Department of Environmental Quality Division of Radiation
Control Radioactive Material License". License #UTI900479. June 2010
Where Addressed in Other Documents
GWDPIV.L
Attachment 7
Standard Operating Procedure SFC Alternate Feed Management
No.: PBL-8 ENERGY FUELS RESOURCES (USA) INC.
Rev. No.: R-O STANDARD OPERATING PROCEDURES Page 1 of 8
Date: August 27, Title: SFC Alternate Feed Management
2013
1.0 Purpose
The following procedure applies to acceptance of alternate feed material(s) which Energy
Fuels Resources (USA) Inc. (EFRI) determines to potentially contain levels of thorium
that require worker safety and/or environmental protection measures over and above
those required for conventional ores or other alternate feed materials. This procedure
may be amended, subject to approval by EFRI's Safety and Environmental Review Panel
(SERP) from time to time, as appropriate to incorporate information and results obtained
from the evaluation of health physics surveys, monitoring and controls implemented to
keep radiological exposures to employees, the public and the environment As Low As
Reasonably Achievable (ALARA).
The methods set forth in this Standard Operating Procedure (SOP) are based on the
assumption that the Sequoyah Fuels Corporation (SFC) material(s) will be delivered to
the White Mesa Mill in Supersaks in poly-lined shipping boxes in an enclosed trailer or
flatbed. Should the delivery method be modified, EFRI will revise this SOP to address
the selected mode of delivery.
2.0 Ore Receiving
For material receiving procedures, see Section 2.0 of White Mesa Mill SOP PBL-9, End
Dump Trailer Acceptance, Handling and Release.
3.0 Ore Dumping
1. The trailer containing the SFC material will enter the Restricted Area at the
Scalehouse gate and proceed to the scales and weighed.
2. After weighing the load, the truck and trailer will proceed to the designated
unloading site.
3. At the unloading site, the trailer will either be opened or the tarp removed from
the flatbed. The Radiation Safety Officer (RSO), or their designee, will perform
an entrance beta/gamma survey on the material and will document those findings
on an Alternate Feed Receipt Inspection form. These forms will be maintained
within the Radiation Department.
4. After the inspection process by the Radiation Staff, the load will be off loaded.
5. After all material has been removed from the trailer, the now empty transport will
return to the Scalehouse for an empty weight.
6. The conveyance will then enter the decontamination process.
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7. Use a front-end loader or similar equipment to push the bags of material into the
designated ore lot pile.
8. Once an ore lot pile is complete, label the pile with the appropriate ore lot number
and cover.
9. Gross alpha, beryllium, arsenic and lead air sampling will be performed
continuousl y, as indicated in Section 7.1 of this SOP, during initial phases of
material receipt in order to determine the exact frequency of monitoring and the
required (Personnel Protective Equipment) PPE to be used. A Radiation Work
Permit (RWP) will be issued during the initial receipt of the SFC feed material(s).
The RWP will list the health physics controls, required PPE, monitoring and
survey requirements necessary to assess the radiological and health exposure
potential to employees operating under the RWP. The air sampling data
collected, as described in Section 7.1 of this SOP, will also be among the data
used to ensure that the stabilization methods listed below are adequate.
10. Dust suppression measures will include the following:
a. The stockpile will be wet down at least once per day until such
time that it is covered.
b. The completed stockpile will be covered with native soils or
another suitable material to provide a cover of the stockpile to
reduce the potential of dusting and provide a temporary radiation
cover.
c. All stockpiles will be inspected at least once per day to ensure the
integrity of the covering.
d. In the event of wind speeds in excess of 20 MPH, all dumping
activities will cease immediately.
4.0 Radiation Monitoring during Ore Processing
Due to the potential for higher concentrations of thoron and other potential radiological
hazards during SFC processing, the following monitoring methodologies will be followed
while processing SFC mill feed. Based upon results of monitoring and dose calculations
and recognizing that there may be a potential for higher than normal radiological
exposures, the Mill RSO may recommend that personnel be rotated from area to area
periodically in order to reduce potential exposure.
As soon as the results of the monitoring activity, conducted in accordance with the
conditions indicated by the RWP, have been evaluated, the added radiological surveys
applicable to the particular SFC material will be established, communicated to the
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Radiation Safety Technicians (RSTs), conducted, and documented. Irrespective of the
added surveys selected, the following radiological surveys will be performed routinely
for the duration of the receipt of SFC material.
4.1 Area Ai rborne Sampling
Weekly area airborne sampling will be conducted in the areas of the Mill listed
below. Also, an eight hour air sample will be collected at a flow rate of 40 liters
per minute, or greater. After sufficient data has been collected and reviewed by
the RSO and ALARA Committee, area airborne sampling frequency may be
reduced to once every two weeks during the receiving of SFC mill feed.
1. Ore Storage area.
2. Leaching area.
3. Central Control Room.
4. SX Building.
5. Precipitation area.
6. Yellowcake drying area.
7 . Yellowcake packaging area.
The above samples will be analyzed for gross alpha, beryllium, arsenic and lead.
4.2 DAC Determination
A composite feed sample will be analyzed for radioscopic composition for V-Nat
and Th-Nat. A composite of two air samples from each of the above locations
will also be analyzed for V-Nat and Th-Nat. The composite air sample results
will be compared to the feed material results. These data comparisons will be
used by the RSO to establish the appropriate derived air concentrations (DAC) for
each location listed above, and the V-Nat to Th-Nat ratio for analysis using gross
alpha counting. If gross alpha counting of air samples using the V-Nat to Th-Nat
rations indicate an airborne radioactive dust concentrations of 25 % of the derived
DAC or the geometric mean of the mixture, in any of the areas listed above, then
the air sample frequency will be increased to weekly in those areas only.
4.3 Breathing Zone Sampling
a. Breathing zone air samples will be collected once per month on
select individuals who perform routine work tasks associated with
processing operations.
b. Breathing zone air samples will be collected from individuals who
perform work tasks under an RWP.
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c. In addition to the above sampling under (a) and (b), further
breathing zone samples may be collected from individuals at the
discretion of the RSO.
d. Samples will be analyzed for gross alpha, beryllium, arsenic and
lead.
4.4 Environmental Sampling
a. Continuous air samples will be collected on a weekly basis in the following
areas during processing of SFC feed material.
i. Ore Storage area.
11. Tailings area.
4.5 Tailings Management
Tailings resulting from the processing of SFC alternate feed material will be
deposited in an area of the tailings system that will ensure that the material is fully
submerged beneath pond liquid and/or tailings slurry from non-SFC alternate feed
materials until such time as the first layer of interim cover or random fill is placed
on the tailings system. This will minimize the potential for thoron gas to escape
to the atmosphere. Mill Management and the RSO will coordinate efforts to
ensure that operations personnel are provided direction regarding placement of
SFC tailings. In addition, the weekly tailings inspections reports will document
the placement of SFC tailings during the preceding week.
4.6 Surveys For External Radiation
a. All employees working with SFC material will wear a personal radiation
monitoring device. The devices will be collected quarterly and the results
entered on individual exposure forms.
b. Beta/gamma dose rate measurements will be performed weekly in all areas
of the Mill operations. These data will be used to perform monthly dose
rate calculations.
c. Monthly personal radiation monitoring devices will be worn by
individuals who perform work tasks that are anticipated to exhibit the
highest potential dose rate exposures, such as those assigned to RWP tasks
and workers performing initial receipt and handling of the SFC material,
prior to establishment of material-specific DAC values.
4.7 Surveys for Radon-222, Radon-220 and Their Daughters
Monthly measurements of radon daughter concentrations for both Ra-222 and Ra-
220 will be conducted in those areas of the Mill listed above in Section 4.1 of this
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SOP. If radon daughter concentrations from either the uranium or thorium parent
are greater than 25% of the limit (0.08 working level for Ra-222 or 0.25 working
level for Ra-220) the sampling frequency will be increased to weekly in areas
where these levels are routinely encountered. All ventilation systems in the Mill
will be checked daily by the radiation safety staff.
5.0 Decontamination and Release of Conveyances
For conveyance release procedures, see White Mesa Mill Standard Operating Procedure
PBL-9, End Dump Trailer Acceptance, Handling and Release.
6.0 Hazard Identification and Safety
In addition to the usual safety procedures required for work at the Mill, the following
safety procedures are to be followed for projects involving SFC materials.
6.1 Required Personnel Protective Equipment
In all areas of the Mill covered by this procedure, hard hats, safety glasses and
steel-toed shoes are required as a minimum. These must be worn in all areas of
the Mill with the exception of the Administration Building.
The following are required while handling SFC material.
1. Coveralls. Coveralls must be laundered on a daily basis.
2. Rubber gloves.
3. Rubber Boots.
4. Respiratory protection as directed by the RSO or specified in an
RWP. Respiratory protection will be used during initial receipt
and handling of SFC feed material(s) and until material-specific
DAC values are set. In addition, all individuals who work in areas
where there is a likelihood that the airborne concentration DAC
limits for either uranium, radon, thoron or thorium will exceed
25% of the DAC will be required to wear respiratory protection, as
directed by the RSO (See section 7.1.2), below.
6.2 Indo trial Hazards and Safety
1. Use caution when operating on the Ore Pad.
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2. Ensure that all personnel within 50 feet of the area where the truck is
backing up or moving.
3. During unloading operations, make sure that the conveyance is
blocked to prevent movement and the ignition is turned off.
4. Be aware of the movement and operation of the use of forklifts or
loaders in the area. Before placing the equipment in reverse, signal by
using two audible alarms with the horn. Then backup with caution.
5. Be aware of high-pressure wash water.
6. Be aware of slippery conditions on the ore pad during periods of
inclement weather.
7. Be aware of the potential for ice build-up on and around the
decontamination pad during periods of cold weather.
8. Use caution when entering or exiting equipment. Be sure to use the
ladders and hand rails. Do not jump off of the equipment.
7.0 Radiological and Environmental Concerns
Environmental radiation monitoring is routinely performed at the White Mesa Mill at
sufficient frequency (quarterly and semiannually) that any potential impact to the public
and or the environment would be identified. In addition to the environmental air
monitoring samples collected continuously at the Mill and analyzed for radioisotopes U-
Nat, Ra-226, th-230 and Pb-210, the air samples collected during receipt, handling,
processing and disposal of SFC materials will also be analyzed for Th-230, Ra-228 and
Th-228. The RSO will evaluate the resulting data and compare the results to their
respective effluent concentration limits contained in 10 CFR Pmt 20, Appendix Band
will retain records of these evaluations at the Mill for State of Utah DRC inspection.
7.1 Airborne Radiation Protection
1. Until otherwise indicated by air sampling results and agreed upon by the
Mill RSO and the ALARA Committee, the areas of the ore storage pad
used for SFC material will be posted as either a "Radiation Area" and/or
"Airborne Radioactivity Area" in accordance with 10 CFR 20.1902.
2. All personnel involved with material handling will be required to wear a
full face respirator, until such time that review of the air samples by the
RSO and ALARA committee indicate that this level of protection is not
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needed. Employees will be notified of any changes to the respiratory
protection requirements by memorandum.
3. Subsequent to approvals by the RSO and ALARA Committee for reduced
posting, if, based on air sampling, an area exhibits 25% of the DAC limits
for either uranium or thorium, it will be posted "Respiratory Protection
Required".
4. All individuals who work in areas where there is a likelihood that the
airborne concentration DAC limits for either uranium, radon, thoron or
thorium will exceed 25% of the DAC, or where there is a potential for
elevated beryllium, arsenic or lead, will be required to wear respiratory
protection. As directed by written memorandum from the RSO, one of the
following respirators will be selected:
i. Full Face Respirator
11.. Powered Air Purifying Respirator (P APR)
111. Self Contained Breathing Apparatus (SCBA)
Respirator usage will remain in effect for all areas where elevated readings
for any of the above parameters have been found until laboratory analysis
indicates that the operations no longer pose a health risk.
5. Personal air monitoring will be conducted as per Section 1 of the White
Mesa Mill Radiation Protection Manual and Sections 4.2 above.
6. Continuous air sampling will be conducted around the perimeter of the ore
pad. At the onset of the SFC project, sample filters from the continuous
air samplers will be collected and analyzed for gross alpha, Ra-222 and
Ra-220 on a weekly basis. This frequency may be relaxed upon approval
of the site RSO and the ALARA Committee.
7. Real time thoron monitors will be placed around the periphery of the ore
pad for the duration of the SFC project. These monitors will be changed
out according to the frequency recommended by the manufacturer and
analyzed for Ra-220.
7.2 Urinalysis
All personnel involved with the dumping and stockpiling or processing of SFC
content material and RST's involved in monitoring described in this SOP will
submit a urine sample every two weeks at a minimum, or at a greater frequency if
so directed by the provisions of an RWP. These samples will be analyzed for
uranium and thorium content. Evaluation and con'ective actions will be
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conducted pursuant to guideline provisions contained in Regulatory Guide 8.22
Bioassay at Uranium Mills. In vivo lung counting may be implemented if
circumstances suggest an overexposure or uptake of either uranium or thorium
has occurred. In vivo counting will be conducted at the discretion of the RSO and
ALARA Committee.
7.3 Personal Hygiene
1. All personnel involved with the dumping, stockpiling or processing of
SFC material will be required to wear designated coveralls. These
coveralls will be changed and laundered on a daily basis.
2. All personnel involved with the dumping, stockpiling or processing of
SFC material will be required to shower before leaving the restricted area
ta the end of their shift.
3. All personnel will survey their hands, boots and clothing for surface
contamination prior to eating or leaving the restricted area.
AppendixB
Gamma Field Data for Supersaks Stored at Gore Oklahoma Facility
<)rC
Radiological Dose Rate Survey Form ~----------------------------------------~------"
Page 1 of 1
w
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South Yellowcake
Storage Pad
~
Survey Date: 2/11/2013 TIme: 10:45 LocaUon: [Raffinate Storage ~ -Instruments and Counters Used
Type. Seriat Number Cat Due Date Type Serial Number Cat Due Date
RO-2 5825 7/24/2013 ---------------Conlact 12 Inches
Corr Beta Gamma ~ Gamma
No. mrem/hr (mR/hr) (mR/hr) Location
1 2.2 1.4 N/A 1.0 Cell H
2 1.8 1.7 I 1.3 Cell C
3 1.8 1.9 1.4 Cell B
4 2.2 1.8 1.5 Cell 0
5 2.2 1.2 0.8 Cell EE
6 ----------<.2 General Area
7 1.8 1.6 1.2 Cell F
8 1.4 2.0 1.6 Cell G
9 1.4 1.8 1.0 Cell A
10 ----------<.2 Fenceline
11 N/A N/A N/A N/A
12
13
14
15
16
Remarks:
Surveyor Signature Reviewed By I Date: ,
-~ IfHA ~V:A~ .I
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Appendix C
Technical Evaluation Report For NRC License Amendment 7
TECHNICAL EVALUATION REPORT
DOCKET NO. 40-8681 LICENSE NO. SUA-1358
DATE: August 21, 1998
LICENSEE: International Uranium (USA) Corporation
FACILITY: White Mesa Uranium Mill
PROJECT MANAGER: James Park
TECHNICAL REVIEWER: Duane Schmidt
SUMMARY AND CONCLUSIONS:
As part of its corrective actions taken in response to a Notice of Violation (NOV) issued by NRC
on August 12, 1997, International Uranium (USA) Corporation (lUG) requested an amendment
to Source Material License No. SUA-1358 for the White Mesa uranium mill. By letter dated
December 3,1997, IUC requested approval of a proposed modification to the in-plant air
monitoring program committed to in its approved license application. IUC provided additional
information by letter dated March 23, 1998, in response to comments received from the NRC
staff.
The staff has reviewed IUC's proposal and found it acceptable with slight modifications. These
modifications were discussed with IUC and agreed to in a telephone call on July 20, 1998.
DESCRIPTION OF LICENSEE'S AMENDMENT REQUEST:
By letter dated December 3, 1997, IUC requested an amendment to SUA-1358 to modify
in-plant air monitoring commitments made in its approved license application. IUC's request
was part of its corrective actions taken in response to an NOV issued by the NRC on August
12,1997, as a result of the staff's routine inspection of the White Mesa mill on July 15-17,1997.
By letter dated March 23, 1998, IUC provided additional information in response to a
February 13, 1998, written request from the NRC staff.
By its submittals, IUC proposed that License Condition 11.4 of SUA-1358 be revised, in part, to
require that (1) annual air samples be taken, during operational periods, in routinely or
frequently occupied areas and analyzed for gross alpha radioactivity, and (2) isotopic analyses
of operational mill feed or production product be performed for natural uranium, thorium-230,
radium-226, and lead-210 to assess the composition of air particulates.
Depending on the results of the isotopic analyses, derived air concentration (DAC) values would
be determined for different mixtures of radionuclides, with the result that various areas in the
mill would have a DAC value applied that is most appropriate for the radionuclide mixture likely
to be present in air samples in that area. IUC considers that the mill site can be separated into
Enclosure 1
four areas for this purpose: (1) the ore handling and storage area, where uranium and its
progeny is expected to be in equilibrium; (2) the uranium precipitation circuit, where only soluble
uranium is expected to be present; (3) the uranium drying, packaging, and calciner area, where
only uranium in a moderately insoluble form would be present; and (4) the tailings area, where
uranium and its progeny would be present in disequilibrium, as separation has been attained.
I UC stated that approval of its proposed modifications will result in the collection of more
meaningful isotopic data than that currently collected, and at a reduced expense to the
company.
TECHNICAL EVALUATION:
Currently, in its approved license application, IUC has committed to taking an annual
eight-hour, in-plant airborne radioactivity sample and analyzing the sample for natural uranium,
thorium-230, radium-226, lead-210, and polonium-210. In accordance with License Condition
No. 11.4, IUC is authorized to eliminate this annual sample, during extended periods of mill
standby, if routine airborne sampling show levels below ten percent of the appropriate 10 CFR
Part 20 limits.
At issue in the licensee's proposal is an appropriate method for performing measurements to
determine the isotopic composition of the airborne radioactive particul~tes in plant areas to
which workers are, or may be, exposed. As a result of the uranium extraction process in the
mill, the concentrations of the airborne radioactive particulates are expected to vary around the
mill. Appropriate area-specific DACs (based on the mixture of radionuclides present) can be
used (1) to determine whether measured air particulate concentrations (often gross alpha
measurements) are acceptable, and (2) in the determination of worker radiation exposures.
These determinations are necessary primarily for the licensee to ensure compliance with the
worker dose limits of 10 CFR Part 20, Subpart C.
IUC believes that the ability to sample much larger quantities of the mill feed or product
materials would provide at least as accurate information regarding the radionuclide composition
of potential airborne contaminants as does the current air sampling method. The NRC staff
agrees that the larger sample sizes possible with the proposed method should improve the
validity of the results on radionuclide composition.
The staff also considers that the sampling of the mill feed materials should allow for the early
identification of materials that are significantly different, in terms of radionuclide composition,
from natural ores processed at the mill, an issue of some importance considering the
processing of alternate feedstock materials. As a result, IUC would be able to evaluate the
need for changes to DAC values for various areas of the plant commensurate with the material
being processed. Thus, the NRC staff concludes that the proposed approach should be valid
for the purpose of determining DAC values for the different areas of the mill. The staff cautions
that the use of this approach depends on accurate determinations, in advance, of how the
isotopic composition of the mill feed and product may impact the isotopic composition of air
particulates in the different mill areas.
2
A second issue with the proposed license amendment is the appropriateness of the proposed
approach for extended periods of mill standby. IUC did not specifically address this issue in its
submittals. However. during mill standby, there would be no mill feed or product to sample.
Thus, it appears to the NRC staff that, if isotopic results are needed for DAC or dose
calculations during periods of standby, the licensee can make use of previously determined
values, or base calculations on other knowledge of the likely airborne contaminants during
standby conditions. Such an approach would generally be acceptable.
Finally, approval of this request will not impact the regular weekly and monthly in-plant radiation
monitoring conducted by IUC.
Therefore, the staff finds lUG's proposed approach to be acceptable. However, the staff
considers that an annual analysis of mill feed or product materials may not be frequent enough,
in light of lUG's past and anticipated future processing of various alternate feed materials in
addition to natural uranium ore. Therefore, the staff will require that IUC perform an isotopic
analysis of mill ·feed or product materials any time a new feed material is introduced into the mill
process. lUG agreed to this modification by telephone on July 20, 1998.
RECOMMENDED L1GENSE GHANGE:
License Condition 11.4 of SUA-1358 will be modified, in part, as follows:
Annually, the licensee shall collect, during mill operations, a set of air samples covering
eight hours of sampling, at a high collection flow rate (Le., greater than or equal to 40
liters per minute), in routinely or frequently occupied areas of the mill. These samples
shall be analyzed for gross alpha. In addition, with each change in mill feed material or
at least annually, the licensee shall analyze either the mill feed or production product for
U-nat, Th-230, Ra-226, and Pb-210 and use the analysis results to assess the
fundamental constituent composition of air sample particulates.
[Applicable Amendment: 7]
ENVIRONMENTAL IMPACT EVALUATION:
Because this change in lUG's in-plant radiation monitoring program will not result in
(1) a significant change or increase in the types or amounts of effluents that may be released
offsite; (2) a significant increase in individual or cumulative occupational radiation exposure;
(3) a significant construction impact; or (4) a significant increase in the potential for or
consequences from radiological accidents, an environmental review was not performed since
actions meeting these criteria are categorically excluded under 10 CFR 51.22(c)(11).
3