DRC-2011-002212 - 0901a06880208ebe

C-2011-002212
DENISO
MINES
February 28, 2011
Received
MAR 201
Division of
Radiation Conlrn!
Denison Mines (USA) Corp.
105017th Street, Suite 950
Denver, CO 80265
USA
Tel: [phone]
Fax ; 303 369-4125
www.denisonmines.com
07'
VIA E-MAIL AND OVERNIGHT DELIVERY
Mr, Rusty Lundberg
Executive Secretary, Utah Radiation Control Board
Utah Department of Environnnental Quality
195 North 1950 West
P.O. Box 144850
Salt Lake City, UT 84114-4850
Re: White Mesa Uranium Mill; Radioactive Materials License No. UT190047g - Safety and
Environmental Review Panel ("SERF") 2010 Annual Report
Dear Mr. Lundberg:
Enclosed please find the 2010 Annual SERP Report for the White Mesa Mill, which is being submitted in
compliance with condition 9.4 C of State of Utah Radioactive Materials License No. UT 1900479.
Please contact the undersigned if you have any questions or require any further information.
Yours very truly,
DENISON MINES (USA) CORP.
Jo Ann Tischler
Director, Compliance and Permitting
cc: David C. Frydenlund
Ron F. Hochstein
Harold R. Roberts
David E. Turk
Katherine A. Weinel
N:\Required Reports\SERP Reports\2010 SERP Reports\02.21.11 Transmittal 2010 Annual SERP Report.doc
February 28, 2011
VIA E-MAIL AND OVERNIGHT DELIVERY
Mr. Rusty Lundberg
Executive Secretary, Utah Radiation Control Board
Utah Department of Environmental Quality
195 North 1950 West
P.O. Box 144850
Salt Lake City, UT 84114-4850
Denison Mines (USA) Corp.
1050 17th Street, Suite 950
Denver, CO 80265
USA
Tel: [phone]
Fax: [phone]
www.denisonmines.com
Re: White Mesa Uranium Mill; Radioactive Materials License No. UT1900479 -Safety and
Environmental Review Panel (USERP") 2010 Annual Report
Dear Mr. Lundberg:
Enclosed please find the 2010 Annual SERP Report for the White Mesa Mill, which is being submitted in
compliance with condition 9.4 C of State of Utah Radioactive Materials License No. UT 1900479.
Please contact the undersigned if you have any questions or require any further information.
Yours very truly,
DENISON MINES (USA) CORP.
~~ ~ Ann Tischler
Director, Compliance and Permitting
cc: David C. Frydenlund
Ron F. Hochstein
Harold R. Roberts
David E. Turk
Katherine A. Weinel
N:\Required Reports\SERP Reports\2010 SERP Reports\02.21.11 Transmittal 2010 Annual SERP Report.doc
WHITE MESA MILL
SAFETY AND ENVIRONMENTAL REVIEW PANEL (SERP)
2010 ANNUAL REPORT
February 28,2010
Submitted to the Utah Department of Environmental Quality
Division of Radiation Control
Submitted by:
Willte Mesa Uranium Mill
License No. UT 1900479
1. INTRODUCTION
This report is being submitted by Denison Mines (USA) Corp. ("DUSA"), licensee of the White
Mesa Uranium Mill (the "Mill") to the Utah Division of Radiation Control ("DRC") in
compliance with condition 9.4 C of State of Utah Radioactive Materials License No. UT
1900479 (the "License").
There were two Safety and Environmental Review Panel ("SERP") evaluations conducted for the
period of January 1,2010 through December 31, 2010. Each SERP evaluation and review was
conducted in accordance with SERP procedures set forth in the Mill's Standard Operating
Procedure PBL-1, Rev. No. R-4 (the "SERP SOP"). The evaluations are summarized below in
Section 2.
2. SUMMARY OF EVALUATIONS
This section describes the changes, tests, or experiments evaluated by the SERP pursuant to
License condition 9.4, and summarizes the evaluations performed and actions taken by the SERP
relative to each.
In each case, the SERP consisted of those individuals specified in License condition 9.4 C, with
additional members included as appropriate, to address technical aspects.
The SERP followed the SERP SOP as it performed its evaluations, to ensure that the actions
taken satisfy the following 3 conditions specified in License condition 9.4 B:
a) The change, test or experiment does not conflict with any requirement specifically stated
in the License, or impair the licensee's ability to meet all applicable regulations.
b) There is no degradation in the essential safety or environmental commitments in the
License application or provided by the approved reclamation plan.
c) The change, test or experiment is consistent with the conclusions of actions analyzed and
selected in the Environmental Assessment dated February 1997 (the "1997
Environmental Assessment).
2
2.1. SERP Report No. 2010-01 December 16, 2010 Revisions to Bioassay Standard
Operating Procedure
2.1.1. Proposed Action
Review and approval of changes to the Standard Operating Procedures for Radiation
Monitoring -Personnel, PBL-RP-1, Rev. No. DUSA-5, Book No.9, relating to bioassay
standard operating procedures (the "Bioassay Change").
2.1.2. Description of Change, Tests or Experiments
The existing Standard Operating Procedure (the "Bioassay SOP") was based on performing on-
site testing of samples in the Mill's older fluorometer and/or ICP-MS instruments, which are no
longer in use. These instruments have been replaced by a newer on-site instrument which meets
the requirements in NRC Reg. Guide 8.22. The new on-site instrument has also been quality
checked against analyses performed by the outside contract laboratory, Energy Labs ("EL"),
which is certified for bioassay of uranium in urinalysis samples. The SERP evaluated
modifications to Section 1.4 of SOP PBL-RP-1 of the Radiation Protection Manual to allow use
of the new on-site instrumentation.
2.1.3. Safety and Environmental Evaluation ofthis SERP Action
In making their determination, the SERP reviewed the following information and considered the
following issues.
In summary:
• The Bioassay Change does not create any new emissions or sources.
• The Bioassay Change does not generate any new occupational safety issues.
• The Bioassay Change is a more modern technology which produces more dependable
results than the technology previously in use at the Mill.
• The instrumentation provides results that have been verified by parallel testing at an
outside laboratory certified for uranium bioassay in urinalysis.
• The Bioassay Change is consistent with the requirements of NRC Reg. Guide 8.22
• The Bioassay Change is consistent with the text in Section 6.4.5 ofthe February 28,2007
License Renewal Application (the "License Renewal Application") and its references to
the Radiation Protection Manual.
The SERP concluded that:
a) The Bioassay SOP satisfies the requirement set out in License condition 9.6 that
SOPs shall be established and followed for all operational process activities involving
radioactive materials. The SERP confirmed that the License Renewal Application
does not prescribe any specific instrumental method for urinalysis. The license
renewal application commits to compliance with Reg. Guide 8.22 and refers to
3
Section 1.4 of the Radiation Protection Manual Book 9, which contains the SOP
section under review in this SERP. The new ICP-MS meets the requirements of Reg.
Guide 8.22. The Bioassay Change, therefore, does not conflict with any requirement
of the License.
b) The changed Bioassay SOP will not produce any degradation in the essential safety or
environmental commitments in the License application, and, in fact, provides more
accurate and dependable results for the urinalysis program that is required to meet
worker safety commitments or provided by the approved reclamation plan. Therefore
this criterion is met.
c) The changed Bioassay SOP is not expected to produce any environmental impacts
beyond those assessed in the EA dated February 1997, and is consistent with the
conclusions regarding actions analyzed in the EA. As a result, this criterion is also
satisfied.
2.1.4. SERP Action
The SERP concluded that the Bioassay Change meets the criteria set forth in the SERP SOP for
approval, and approved the Bioassay Change. No changes to the License or License Renewal
Application text will be required. Redlined and clean black-line versions of the revised SOP
PBL-RP-1 are provided in Attachment 1.
The SERP also noted that as a result of Division of Radiation Control ("DRC") inspections
during 2010, DRC personnel recommended that the Radiation Protection Manual be changed to
add the use of electronic calibration for both the breathing zone and airborne area monitors, in
addition to the current bubble tube calibration method.
The SERP agreed to an administrative change to SOP-PBL-RP-3 to add the needed method into
a new section, entitled Section 3.3.4. A redlined (track changes) version of changes to SOP-
PBL-RP-3 has been attached to this report.
Redlined and clean black-line versions of the revised SOP PBL-RP-3 are provided in Attachment
2.
4
2.2. SERP Report No. 2010-02 December 16, 2010 Replacement of Propane with
Liquefied Natural Gas ("LNG")
2.2.1. Proposed Action
Review and approve the proposed plan to switch the Mill's primary heating and burner fuel from
propane to liquefied natural gas ("LNG"), and identify any changes that may be necessary to
Plans, Standard Operating Procedures ("SOPs"), and other Mill documentation to address the
proposed change to LNG (the "LNG Change").
2.2.2. Descriptions of Change, Tests or Experiments
The Mill currently bums propane for burner fuel in three of the Mill's boilers, three dryers, the
Fusion Furnace and the Rotary Calciner. The Mill has evaluated the use of an alternative fuel,
LNG, and the Mill proposes to switch to LNG fuel during the winter of2011.
Denison will replace the current burner orifices in the North and South Yellowcake Dryers,
Vanadium Dryer, Ammonia Meta-vanadate Dryer, Fusion Furnaces, and three boilers on site
with larger orifices capable of firing LNG. The LNG supplier will add a new insulated cold
storage tank and vaporizer in a new storage area east of the existing propane tank. The tank will
be piped to a new LNG vaporizer. The vaporizer will be piped to the existing fuel gas pipe
manifold that currently supplies the burner orifices in the equipment listed above.
2.2.3 Safety and Environmental Evaluation ofthis SERP Action
The SERP reviewed the LNG Change described above and concluded that:
The LNG Change does not conflict with any requirements specifically stated in the License, or
impair Denison's ability to meet all applicable regulations.
a) The SERP reviewed information indicating that LNG would create no change to the
combustion or stack temperatures of any of the affected burner equipment. There will be
no change to the total BTU combustion rate and no change to the stack configurations or
emissions control equipment.
b) LNG is generally safer to handle than the currently used propane. Use of LNG would
require development of appropriate health and safety procedures to prevent freeze bums
around cryogenic equipment.
c) Like propane, spills of LNG would not produce free liquid or runoff and would require
no changes to spill management procedures.
d) The SERP identified that the following plans and procedures would need to be revised to
address the proposed LNG Change:
5
• Utah Air Approval Order (in progress);
• SOPs for the North and South Yellowcake Dryers, the Ammonium Meta-Vanadate
Dryer, the Fusion Furnace, the Rotary Calciner, and three boilers. An additional SOP
may need to be prepared for prepping the fuel storage and manifold system for
changeover from propane to LNG and vice versa;
• The Mill's Spill Prevention, Control, and Countermeasures ("SPCC") Plan
• Other sections of License Renewal Application;
• The Mill's Emergency Response Plan; and
e) One MSDS would need to be added to any of the above documents which contain
MSDSs and locations in the Mill which provide MSDSs for fuel materials.
2.2.4 SERP Action
The SERP concluded that:
a) The LNG Change does not contlict with any requirement specifically stated in the
License, or impair the ability to meet all applicable regulations. The Change is
consistent with the license subject to a few minor changes to the appendices to the
application. Denison has also discussed the proposed change with the Utah Division
of Radiation Control ("DRC"), and DRC has concluded that there were no issues
relative to license.
b) The LNG Change will not produce any degradation in the essential safety or
environmental commitments in the License Renewal Application or provided by the
approved reclamation plan. The proposed change will not produce any new
environmental emissions and is expected to reduce the Mill's combustion-related
emissions. The proposed Change will not produce any additional respiratory hazards
beyond those already managed at the Mill in connection with propane.
c) The LNG Change is not expected to produce any environmental impacts beyond
those assessed in the EA dated February 1997, and is consistent with the conclusions
regarding actions analyzed in the EA, specifically that the Mill would use light liquid
hydrocarbon fuel for fired heaters in the Mill process. As a result, this criterion is
also satisfied.
The SERP concluded that the LNG Change meets the criteria set forth in the SERP SOP for
approval, and approved the LNG Change. The SERP authorized implementation of the LNG
Change and determined that revisions will be made to the plans and documents identified in
Section 4, above. The LNG Change will not be implemented until approval has been received
from Utah DAQ through a revised Air Approval Order. Changed pages to the plans and
documents identified in Section 4, above, will be provided to DRC upon revision of those
documents.
6
ATTACHMENT 1
7
White Mesa Mill -Standard Operating Pro~edures
SOP PBL-RP I
Date: IGi/lO Revision: DUSA-4 ~~
Book 9: Radiation Protection Manual. Section I Page lor 19
1.0 RADIATION MONITORING -PERSONNEL
This section contains the following procedures for personnel radiation monitoring
including: (I) airborne paniculates (2) alpha surveys (3) beta/gamma surveys and (4)
urinalysis surveys.
1.1 AIRBORNE PARTICULATES
Sampling for personnel exposure to airborne paniculate radionuclides, other than for
radon progeny, will be done utilizing two distinct sampling protocols: (l) personnel
breathing zone samplers. and (2) ambient air high volume samplers. Specific standard
operating procedures for these two collection methods are described in Section 1.1.2 and
1.1.3 below.
1.1.1 Frequency
For work where there is the potential to cause airborne radiation doses to site personnel,
the frequency and type of air sampling to be conducted is detennined from measured air
concentrations:
0.01 DAC -0.1 DAC Quanerly or monthly area air sampling and/or bioassay
measurements
> 0.1 DAC Continuous sampling is appropriate if concentrations are
likely to exceed 0.10 DAC averaged over 40 hours or
longer.
The RSO will detennine the exact frequency of area air sampling. breathing zone
sampling and/or bioassay measurements and detennine how many workers in a group of
workers performing similar jobs are to be equipped with breathing zone air samplers.
Higher airborne concentrations warrant more frequent use of area air samplers. bioassay
measurements, and breathing zone air samplers. Area air samplers may be used where
documentation exists showing the sample is equivalent to a breathing zone sample.
Breathing zone samples laken within one foot of the worker's head are considered
representative without funher documentation. Breathing zone air samplers are preferred
under work conditions of higher airborne concentrations. Table 1.1.1·1 below, from
Regulatory Guide 8.25, provides additional guidance for the RSO in designing and
implementing air sampling programs for specific jobs .
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White Mesa Mill -Standard Operaling Procedures
SOP PBL-RP-I
Dale: 1\I~1I0 Revision: DUSA-~.5
Book 9: Radiation Protection Manual. Section I Page 2 of 19
Table 1.1.1-1
Air Sampling RecommendatioN! Based on Estimated Intakes and Airborne Concentrations
Worker's Estimated Estimated Airborne
Annual Intake as a Concentrations as a Air Sampling Recommendations
~ Fraclion of ALI _~...!F..:.r=ac::.:;t~io::..:n..::o::..f-=D:..:.A.!:C:::...-+ ____ _
<: 0.1
> 0.1
Any annual inlake
<0.01
>0.01
<: 0.3
Air sampling is generally not necessary.
However, monthly or quarlerly grab samples or
some other measurement may be appropriate 10
confirm thatllirborne levels are indeed low.
Some air sampling is appropriate. Intermittent or
grab samples are appropriate near the lower end
of the range. Continuous sampling is appropriate
if concentrations are likely to e"ceed 0.1 DAC
averaged over 40 hours or longer.
Monitoring of inlake by air sampling or bioassay
is required by 10 CFR 20. I 502(b).
> 0.3 A demonstration thai the air samples are
representative of the breathing zone is appropriate
if (I) intakes of record will be based on air
sampling and (2) concentrations are likely to
exceed 0.3 DAC averaged over 40 hours (i.e.,
intake more than 12 DAC-hours in a week).
> I
>5
Air samples should be analyzed before work
resumes the ne"l day when potential intakes may
exceed 40 DAC-hours in I week. When work is
done in shiflS, results should be available before
the next shift ends. (Credit may be taken for
protection faclors if a respiratory protection
program is in place.)
Continuous air monitoring should be provided if
there is a potential for intakes to exceed 40 DAC-
hours in I day. (Credit may be taken for
protection factors if a respiratory protection
'projram is in . lace.
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While Mesa Mill . StMdatd Operating Procedures
SOP PBL-RP·\
Dale: 1Il2/1O Revision: DUSA·4,-j.~
Book 9: Radiation Protection Manual, Section 1 Page 3 of 19
1.1.2 Breathing Zone Sampling
1.1.2.1 General
Breathing zone samplers (SKC pumps and accessory kits, or equivalent) are used to
determine airborne exposure to uranium while individuals are performing specific jobs.
The units consist of a portable low volume pump that attaches to the individuals belt,
tygon tubing and filter holder that is attached to the individual's lapel or shirt collar. The
unit monitors airborne uranium in a person's breathing zone. Pumps must be recharged
after 6 to 8 hours of use.
1.1,2.2 Applicability
Breathing zone samples are required:
• for all calciner maintenance activities,
• at least quarterly during routine operating and maintenance tasks on
representative individuals performing these tasks,
• when radiation work permits are issued in which airborne concentrations may
exceed 25% of IOCfR20 limits,
• weekly for yellowcake operations, or
at the discretion of the RSO.
1.1.2.3 Procedure
The procedure for collecting a breathing zone sample is as follows:
I. Secure the breathing zone sampler. which has been charged and loaded with a filtet
paper from the radiation department.
2. Secure the pump to the worker's belt and the filter holder 10 the shirt collar or lapel.
Try to secure pump tubing to minimize restriction of motion.
3. Tum pump on (record the lime pump was turned on) and continue monitoring until
the work being monitored is completed and the worker no longer is in the exposure
area. Record the time at which the job is complete.
4. Return the pump and accessories to the RSO, who will remove the filter paper for
analysis. Be sure to indicate accurately the total time taken by the work being
monitored.
5. Analysis of filter samples will be performed using a sensitive alpha detector. The
procedure is as follows: (a) count a background sample for ten minutes; (b) divide the
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While Mesa Mill Standard Openrting Procedures
SOP PBL-RP-l
Dale: 1112110 Revision: DUSA-+l~
Book 9: Radialion Proteclion Manual. Section 1 Page 4 of 19
background count by ten to obtain the background count rate in cpm; (c) Place the
breathing zone sample in the instrument and count the sample again for ten minutes;
(d) divide the sample count by ten to obtain the count rate in cpm; (e) subtract the
background count rate from the sample count rate; and, (0 record all data on the
Breathing Zone sampling analysis form (a copy of which is attached).
6. Record the total hours of exposure that are being assigned to the employee on the
Employee Exposure fonn, which is maintained in personnel folders. Be sure to
consider protection factors permitted by respirator use if the employee was also
wearing respiratory protection during the job.
7. The number of DAC hours assigned is calculated using the following formula:
DAC hours ;;;; Measured air concentration x Total hours of exposure
of exposure (DAC)(PF)
where: DAC = Derived Air Concentration (for uranium; 10 CFR Part 20,
Appendix B)
PF = protection factor for respirator use. If no respiratory
proteclion was used PF = I.
TIle measured air concentration must be in uCi/cc.
1.1.2.4 Calibralion
Prior to use, calibration of the breathing zone samplers will be done using a calibratipn
method aSllu! 8Yhkle T1l9l! CllhlulIlieR ffil!t~8d. described in Section 3.2,...l..
1.1.2.5 Equipment -Breathing Zone Sampler
The equipment used for breathing zone samples consists of:
I. Personal sampling pumps
2. Gelman 37 mm Delrin filter holders, or equivalent
3. Gelman 37 mm type AlE glass fiber filters, or equivalent
4. Kurz Model 543 air mass flow meter, or equivalent
1.1.2.6 Data Record
Data maintained on file includes:
I. Time on and off for each sample pump.
2. Sampling location(s).
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1 .... """'It~# ""'~J)ItI')4 !!(m4SHll-1t~
While Mesa Mill Slandard Openuing Procedures
SOP PBL-RP-J
DOlle: HI.~/I 0 Revision: DUSA-~ ~ ~
Book 9: Radlalion Protection Manual. Seclion I
3. Individual's name, identification number, etc.
4. Date and sample number.
S. Sample count rate.
1.1.2.7 Calculations
PageS of 19
The airborne concentration in uCi/cc is equal to the sample count rate minus the
background count rate in cpm divided by the instrument alpha efficiency. the sample flow
rate in cc/minute, the sample time in minutes and a conversion factor converting dpm Lo
uCi.
The calculation is:
Equation Number I:
Airborne concentration ;;;; (Count Rate)
(Time)(eft)(conversion factor)(Flow Rate)
i.e. !.!£i = <cpm-Bkg) I uCi ()) (J)
cc (eft)(2.22x 106dpm)(cc/min)(min)
where: efr;;;; cpm/dpm for counting instruments
cpm ;;;; counts/min
dpm = disintegrations/min
conversion factor I uei = 2.22x106 dpm
Flow Rate = cc/min
Collection lime = min
Once the airborne concentration has been calculated it is possible to calculate personnel
exposure in microcuries (uCi). Personnel exposure is determined for an individual who is
working in an area at a known air concentration (uCi/cc) for a given amount of time
(hours) breathing the area air at an assumed rate. The breathing rate for a standard person
(Handbook of Radiological Health) is 1.20 cubic meters per hour (m l/hr).
The calculation for personnel exposure is:
Equation Number 2:
Exposure uCi ;;;; (uCi/cc)(1.20m~lhr)(hours of exposure)(conversion rate)
where: uCi/cc ;;;; air concentration from Equation I
J .20 m"lhr = breathing rate for standard man (ICRP)
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~~ ............. k<'"""_.'"""''''''"_ffitllll_,. t I,I~ •• /ll.'·.,; g~"".II."*,,I~~",,_I' .. oh\llOR1111111l1
1",,"""'I1._.~fl-Af>rl) Ht'M WMMs( >I'-M--+I!lI4,<
White Mesa Mill Standard Operating Procedures
SOP PBL·RP·I
Book 9: Radialion Protection Manual, Section 1
hours of exposure = hours
conversion factor = 106cclm~
Date: IOmo Revision: DUSA-4 .,
Page 6 of 19
It is also possible to detennine the percent or fraction of the Derived Air Concentration
(DAC) for a panicular radionuclide using the infonnation obtained from the exposure
calculation and dividing this value by the regulatory limit DAC listed in 10 CFR Part 20.
% DAC ... Exposure in uCi/uCi limit 10 CFR Part 20
For the natural uranium (U-Nat) the DAC limits from 10 CFR Part 20 for insoluble Class
Y compounds are as follows:
1.1.2.8
• Weekly
• Quarterly
• Yearly
1.0 x 10" uCi/week
1.25 x 10.2 uCi/Qt
5.0 x 10 2 uCilyr
AURA/Quality Control
The RSO reviews each monitored result and initiates action if levels exceed 25% of 10
CFR 20 limits. At a minimum, ten percent (10%) of the air samples collected in a given
quarter will be recounted using the same instrument or using a different instrument and
Ihese results will be compared to the original sample results. Deviations exceeding 30%
of the original sample results will be reviewed by the RSO and the samples will be
recounted again until the sample results are determined to be consistent. Additional QA
samples consisting of spiked air samples, duplicate samples and blank samples will be
submitted to the radiation department for counting. This will be based on ten percent
(10%) of the number of samples collected during a quarter. The sample results will be
compared to the spiked values. duplicate values, or blank (background) values of the
prepared sample. Deviations exceeding 30% of the detennined spiked. duplicate or blank
value will be recounted. If no resolution of the deviation exceeding 30% is made the QA
samples preparation will be repeated. Periodic reviews by the RSO and the ALARA
audit committee will be made and documented to ensure quality maintenance and
ALAR A control.
1.1.3 Airborne High Volume Sampling
Grab air sampling involves passing a representative sample of air through a filter paper
disc via an air pump for the purpose of delennining the concentration of uranium in
breathing air at that location. Although the process is only measuring airborne
concentrations at a specific place and at a specific time, the results can often be used to
represent average concentration in a general area. A high volume sample pump will be
used for this purpose. Samples will be analyzed as per standard gross alpha analysis
procedures using a sensitive alpha detector.
h;\\IIII,Sul' MN;t !..l'J'xI/l •• <l.11') HI"II.I"," 1',.1/. ~1"!Ju"1\l7 1 1\~rl\\'thl",")I~ \,\:ll l\!!pll •• WM W'\(M~' •
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H.,.",..I(_w.U,c; .... H-Aw~\WM-.WMM!;{lI'-Il~~_
White Mesa MiII-Standard Operaling Procedures
SOP PBL-RP·'
Dille: I Olll 0 Revision: DUSA4 ~
Book 9: Radiation Protection Manual. Section I Page 7 of 19
1.1.3.1 Frequency and Locations
The following principles used for the collection of area grab samples must be considered
when collecting a sample in order to obtain a representative air concenlration that workers
may be exposed to during their assigned work tasks.
t. The locations selected for sampling should be representative of exposures to
employees working in the area.
2. For special air sampling, the sampling period should represent the conditions during
the entire period of exposure. This may involve sampling during !he entire exposure
period.
3. For routine sampling. the sampling period must be sufficient to ensure a minimum
flow rate of 40 liters per minute for at least 60 minutes.
4. Sample filters will be analyzed for gross alpha using a sensitive alpha detector.
5. Grab sampling procedures may be supplemented by use of Breathing Zone Samples
for special jobs or non-routine situations.
1.1.3.2 Sampling Equipment
Monitoring equipment will be capable of obtaining an air sample flow rate of at least 40
liters per minute for one hour or longer. Equipment utilized will be and Eberline RAS-I,
or a Scientific Industries ModeJ H25004. or equivalent. Filter media will be of
appropriate micron pore diameter. Equipment is calibrated prior 10 each usage as per
Section 3.{,J of Ihis manual.
1.1.3.3 Sampling Procedure
Steps for collection of area airborne grab samples are as follows:
1. A high volume pump will be used for sample collection.
2. Check sample pump calibration.
3. Locate sampler at designated site. Insert a clean filter, using tweezers, into the filter
holder on the sampler. Do not contaminate the fiUer. Log start time and Mill
operating conditions at the site.
4. Collect a sample for a minimum of 60 minutes at a flow rate of 40 liters per minute.
l ' MJt.Wl' hi:,"," I~ .• ry\ll"!,,, liP K.HII,ti"o I~'" ".00,111)7 I i,cn", !(Whl!>"lI.'i!.S! I AjlJ''' IlJ'M \\'MMspr K.
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, .... _ ~UI~ .......... I~\'~IIIIU'M-WMM<;('" K..l.OiWI
White Mesa MiII-Standard Opemlillg Procedures
SOP PBL·RP-I
Book 9: Radialion Protection Manual. Section I
Dare: wmo Revision: DUSA ,\.~
Page 8 of 19
5. After sampling is completed, carefully remove the tilter, using tweezers, from the
tilter holder and place it in a clean glassine envelope. or in the plastic casing furnished
with the filter.
6. Log all sample data on the log sheet.
A. Sample location and number (also on the envelope).
B. Time on, time off and date.
C. Mill operating conditions at the site.
D. Sampler's initials.
7. Analyze for gross alpha
1.1.3.4 Calculations
Perform calculations as described in Section 1.1.2.1.
1.1.3.5 Records
Logs of all samples taken are filed in the RSO's files. Data are used to calculate radiation
exposures as described in Section 4.0.
Whenever grab sampling results indicate that concentrations in work locations exceed
25% of the applicable value in 10 CFR Part 20. Appendix B, time weighted exposures of
employees who have worked at these locations shall be computed. Calculations will
reveal an individual's exposure in DAC hours. This value shall be assigned to the worker
and logged onto the worker's "Employee Exposure 10 Airborne Radionuclides" fonn.
This form is in Section 4. Whenever special air sampling programs (as required for
cleanup, maintenance, decontamination incidents, etc.) reveal Ihat an employee has been
exposed to airborne radioactive material, the calculated value shall also be entered on the
individual's exposure form.
1.1.3.6 Quality Assurance
Calibration checks on each air sampler. prior to field use, ensure accurate airflow
volumes. Use of tweezers and new filter storage containers minimizes contamination
potential. Field logging of data during sampling and logging of identifying data on
sampled tilter containers minimizes sample transposition. Quality control samples will be
analyzed as described in Section 1.1.2.8
Review of data by the RSO and by the ALARA Audit committee further assures quality
maintenance.
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White Mesa Mill -StDlldard Operating Procedures
SOP PBL-RP-I
Book 9: Radialion Prolection Manual. Section I
1.2 ALPHA SURVEYS
1.2.1 Restricted Area
The Restricted Area is defined as:
Date: I {lJ.JJ 0 Revision: DUSA ~ -~,
Page 9 of 19
I. The property area within the chain link fence sunounding the mill property and the
area enclosed to the north and east of the facility by the posted Restricted Area fence.
2. The active tailings and liquid waste disposal areas.
All personnel who enter the Restricted Area will monitor themselves each time they leave
the Restricted Area and at the end of their shift The Radiation Safety Department will
review the monitoring information. All personnel exiting the Restricted Area must initial
a record of their monitoring activity.
1.2.2 Instrumentation
The instrumentation utilized for personnel alpha scanning is listed in Appendix I at the
end of this manual. Personnel alpha survey instruments are located at the exits from the
Restricted Area.
1.2.3 Monitoring Procedures
The monitoring procedure includes the following steps:
I. The alarm rate meter is adjusted within the range of 500 to 750 dpmJlOO cm2 10
ensure a margin of 250 dpmJlOO cm2 due to the low efficiency of this
instrumentation.
2. An individual monitors himself by slowly passing the detector over their hands,
clothing and shoes. including the shoe bottoms, at a distance from the surface of
approximately ~4 inch. An area that is suspected of possessing any contamination (i.e.
hands. boots. visible spoiling/stain on clothing etc.) shOUld be carefully monitored by
placing the detector directly on the surface and note the measurement.
3. Should an alarm be set off indicating the presence of contamination, the individual
should:
a. Resurvey themselves to verify the contamination.
b. If contamination is present the individual must wash the affected area and
again resurvey themselves to ensure the contamination has been removed.
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White Mesa Mill -Standard Operating i>rocedures
SOP PBL-RP-I
Book 9: Radiation Protection Manual. Seclion 1
Date: 111.1110 Revision: DUSA-4+~
Page 100rl9
4. If the decontamination efforts by the individual are not successful, then the Radiation
Safety personnel will be contacted to assess the situation_ Further decontamination
may be required.
5. If an individual's clothing cannot be successfully decontaminated. they must obtain
clothing from the warehouse to use and must launder the personal clothing in the
laundry room.
6. Individual surveys are to be logged and initialed.
7. Access to and from the Mill's Restricted Area by all Mill workers, contractors and
delivery personnel, other than Radiation. Safety and Environmental Staff, Senior
Laboratory personnel. Mill Management and Mill Supervisory personnel and others as
may be designated by the RSO, will be limited to one or more access points as may be
designated by the RSO from time to lime.
8. A Radiation Technician will be posilioned at each access point designated by the RSO
under paragraph 7 above during peak transition times. such as during breaks and at
the ends of shifts, to observe that each worker, contractor or delivery person is
performing a proper scan. This paragraph 8 will cease to apply to any such access
point if and when one or more automated full body scanners portals or the equivalent
are situated at the access point. which would require workers exiting at that location
to scan themselves by exiting through the portal, and the procedures in this Manual
are amended to incorporate the use and maintenance of such portal or portals.
1.2.4 Training
All employees will be trained on the proper scanning procedures and techniques.
1.2.5 Records
Log sheets will be collected daily and filed by the Radiation staff. Records will be
retained at the Mill. Contamination incidents will result in a written record, which is
maintained on file.
1.2.6 LimilslALARA
Contamination limits for personnel scans are set at 1.000 dpmllOO square centimeters.
Records will be reviewed by the RSO to maintain levels noted as low as reasonable
achievable.
1.2.7 Quality Assurance
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White Mesa Mill Standard Operaling Procedures
SOP PBL-RP-I
Book 9: Radialion Prolection Manual. Seclion I
Date: W~1l0 Revision: DUSA4,.i~
Page II of 19
A random check of an individual's scanning technique provides quality assurance of the
monitoring procedures. Daily function checks using calibrated sources assures
instrumentation performance. Periodic review by the RSO and the ALARA audit
committee document and ensure quality control and ALARA maintenance.
1,3 BETA·GAMMA SURVEYS
Site employees working within the Restricted Area will be required to wear a personal
monitoring device (such as a TLD. LUXEL badge or other NVLAP approved device
which has been approved by the RSO and the SERP) during their work period. The
personal monitoring devices are normally issued to each employee Quarterly; however.
during pregnancy or if the radiological potential for exposure to an individual is
anticipated to be elevated and requires quick assessment the badges may be issued
monthly.
1.3.1 Monitoring Procedures
The monitoring procedures consist of:
I. Personnel issued personal monitoring devices will wear the device on the trunk
(torso) of the body. The personal monitoring device records beta/gamma radiation as
well as other forms of penetrating radiation such as x·rays. A personal monitoring
device is an exposure record of an individual's personal exposure to radiation while
on the job. Therefore. personal monitoring devices are to remain at the Mill and
stored on the assigned dosimeter storage boards. All exposure records obtained by a
personal monitoring device which are not consistent with the exposure rates of work
tasks or work location measurements made throughout the Mill will be evaluated by
the RSO. This evaluation will result in an investigation by (he RSO and a written
explanation of the findings. These written records will be maintained at the Mill.
2. Personal monitoring devices will be issued at a minimum quarterly and will be
exchanged by the Radiation Safety Department. Missing or lost badges will be
reported to management.
3. Female employees that become pregnant and continue to work during the course of
their pregnancy will be placed on a monthly personal monitoring device exchange
during Ihis period. NRC Regulation Guide 8.13 provides guidelines to be followed
during pregnancy and is made part of this procedure.
1.3.2 Records
The Radiation Safety Department will maintain all occupational exposure records in the
departmental files:
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White Mesa Mill · Standard Operating Procedures
SOPPBLRp·1
Book 9: Radiation Protection Manual. Section 1
Date: UIHIO Revision: DUSA-4 ~j
Page 12 of 19
I. Occupational exposure records are a part of an individual's health record and, as such,
will be considered private information.
2. An individual may examine his/her exposure record upon request.
3. An employee terminating his/her employment with Denison Mines (USA) Corp. may
request a copy of his/her occupational exposure records.
4. The Radiation Safety Department on the signature of the employee will request prior
occupational exposure records.
S. Occupational exposure records will be made available to authorized company or
regulatory personnel.
1.3.3 Quality Assurance
Periodic reviews by the RSO and the ALARA audit committee document and ensure
quality control and maintenance of conditions ALARA.
1.4 URINALYSIS SURVEYS
1.4.1 Frequency
Urinalyses will be performed on those employees that are a) exposed to airborne
yellowcake or involved in maintenance tasks during which yellowcake dust may be
produced, or b) routinely exposed to airborne uranium ore dust. Baseline urinalyses will
be performed prior to initial work assignments.
Urine samples are collected on a routine basis from mill employees as required in
Regulatory Guide 8.22. Urine samples will be collected from employees who have
worked in yellowcake packaging, yellowcake precipitation, grind area (SAG mill). ore
feed, sample plant, scale house. and the sample preparation room every two weeks during
production periods. Samples will be collected from all other employees monthly during
production periods. During non· production periods. hi·weekly samples will be collected
if individual exposures are expected to exceed 25% of the DAC value otherwise samples
will be collected from all employees quarterly. Non-routine urinalyses will usually he
performed on employees who have been working on assignments that require a Radiation
Work Permit. and always on any individual that may have been exposed 10 airborne
uranium or ore dust concentrations that exceed the 25% of the DAC level.
1.4.2 Specimen Collection
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White Mesa Mill . Standard Operating Procedures
SOP PBL·Rp·1
Book 9: Radialion Protection Manual, Section I
Dale: 1"~.J10 Revision: DUSA-4,+~
Page 13 of 19
Clean, disposable sample cups with lids will be provided to each employee that will be
required to submit a urine specimen. The containers will be picked up at the
administration building before the individual enters the Restricted Area.
The conlainer, filled with specimen, will be returned to the bioassay laboratory prior to
reporting to work. The name of the employee and the date of collection will be indicated
on the specimen cup.
A valid sample must be collected at least 40 hours, but not more than 96 hours, after the
most recent occupancy of the employee's work area (after two days, but not more than
four days oft).
The specimen should be collected prior to reporting to the individual's work location. To
prevent contamination, the hands should be carefully washed prior to voiding.
Under unusual circumstances where specimens cannot be collected in this manner, the
worker will shower immediately prior to voiding.
1.4.3 Sample Preparation
Equipment required:
15 ml disposable centrifuge tubes with lids
• 10 ml pipette
• I mL pipette
• 200 uL pipette
• 5 ul pipette
• 10 ul pipette
_. _Disposable lips for the above pipettes
• I .000 ppm uranium solution
• Spik.ing solution -. 0.03 or 0.02 gil of uranium in de-ionized water
After the specimens are received, they will be stored in a refrigerator until they are
prepared for analysis.
Sample preparation will be done in an area decontaminated to less than 25 dpm alpha
(removable) per 100 cm1 prior to preparation of samples. All of the equipment that is
used in sample preparation will be clean and maintained in such condition.
A log will be prepared and the following information will be k.ept for each urinalysis
performed:
Sample identification number
r..\\hll SOl' M.,lcr l 'r~ 09 !(.~i.li<'n 1~~l!ll!!.~llill.!lQ;.u,,,,J!.@.l<~:~'15_L!'~.l1.!i'~M_WM1\1Sm'.JI
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While Mesa Mill ., SlDIIdard Operaling Procedures
SOP PBL-RP-l
Book 9: Radialion Proteclion Manual, Seclion I
Name of employee submitting the specimen
Date of sample collection
Date the sample was sent to the laboratory
Date the results were received
Results of the urinalysis in ug/I
Indication of any spike used in ug/I
Dale: 1IWlO Revision: DUSA-~,-
Page 140fl9
The centrifuge tubes will be marked with a sample identification number. 10 milliliters
of urine will Ihen be pipetled into the centrifuge tube using the pipette device. Or I
milliliters of ~~ine Will ,hen be ll~ue !nt9 the ~entriful\c lubl! ysi"!' th!! uipelle deVice
(To prevent contamination, a new tip must be used for each specimen.) After each step of
the procedure, the proper entry must be made in the logbook.
The samples that are to be spiked for quality assurance purposes will then be prepared.
The spikes will be introduced into the sample with 5 ul or 10 ul pipettes. A new tip must
be used with each spike. With the standard spike solution (0.03 gil of U), a 5 ul spike
will result in a I~ ugll concentration for the 10 ml sample; the 10 ul spike will give 30
ugll). The proper entry must be made in Ihe logbook for each sample spiked.
After preparation has been completed, the QA samples are securely packaged as soon as
practicable and sent to the contract laboratory for analysis.
The samples that are to be analyzed in-house will be placed in the chemistry laboratory's
refrigerator until the analysis can be completed. A copy of the in-house analytical
procedure is described in Section 1.4.7.6.
1.4.4 Quality Assurance
To assure reliability and reproducibility of results, at least 25% of the samples that are
submitted for analysis will be used for quality assurance purposes. These samples will
consist of spikes, duplicates. and blanks (samples collected from individuals known to
have no lung or systemic uranium burden).
Spiked samples will be prepared as stated under sample preparation of this procedure.
Duplicates will be identical samples of the same specimen and/or spikes of identical
concentrations.
To assure reliability of the in-house analytical procedure. 10% of the samples will be sent
to a contractor laboratory for analysis. These samples will contain quality assurance
items designed to provide intra-laboratory comparisons.
1.4.5 Analysis
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White Mesa Mill -Standard Operating Procedures
SOP PBL-RP-I
Date: Illm O Revision: DUSA 4 I~
Book 9: Radiation PrOJeclion Manual, Seelion I Page IS of 19
After the samples are collected as outlined in Guide 8_22, they are identified to the lab by
collection date and number. Urinalysis results must be completed and reported to the
Radiation Safely Department within seven days of the sample collection.
1.4.5.1 Equipment List
I. Specimen collection cups with disposable lids (VWR No. 15708-71 I or equivalent)
2. Screw cap, disposable, gradualed 15 ml centrifuge tubes (Coming No. 25310 or
equivalent)
L Micro-pipetles 1 each 5, 5 each 10 microliters (Oxford Model 7000 or equivalent)
.J. -l AdlYl'l.tble Emnol/lclle !!neh 1.000 uL. 200 uL and 5 mL
4, 20 IIlI SeiRlillalieR Vials
5. Disposable micro-pipette tips for micro-pipettes (Oxford No. 9\OA or equivalent)
&, laB OveR
+-Hel Plate
:r;,.(l FumeHood
Q.,.LUllrasonic Cleaner
m::!.PE-SCIEX ELAN DRC II AXIAL FIELD TECHNOLOGY ICP-MS (or equivalent)
9. Po(yscit:nce WIlier Cir£ulillgr (o[cguivall:nl)
10. Perkin-Elmer AS-I Q AulO SamIJIt:r (or equivalent)
II. Thermo Sci~nli lic Vortt:x mix lures (or cguivalcllt)¥el'eefj5 with ellr ... ~€:IliflS
1.4.5.2 ReagenlUSI
I. I % to 2% Nitric Acid
L Concentrated Nitric Acid
2.~_L_QQQ uyml Urantum Stock Solulion, certified vendor preJlarcd
+. PeFi!h1erie AeiE:!, CeAseAlFaleE:! 7Q%
4, Wl!lliA~ Age-AI
S. I.OOQ Ilglml UF8RI\c:Im Sleek SellllleR. ee~IItt!E:! ~'t!RtleF ~re~ared
~, .:I.Dilutions of the above stock solution, replaced bi-annually. Used for QAlQC.
L Appropriate Cleaning Solution for UItTllsonic Cleaner
7· ilJ . )() !'!£Lml,l!ranlllm Stock Solution, ,llllft:hased from certilied \endor to use .IS
~alibration \t.tndard 31 different diltltioll~
Ensure that all reagents used are within their expiration dates listed on each reagent
package, if applicable.
1.4.5.3 Premise
A portion of urine is dilytcd with 2 (X-' Nilrit aC id solution. mixed thomughl~ a!!Q
anal~5led ill Ihe flFeSeAee er 1I-SH'~~~~~t! is ht!aloo--a~
t.llill!..S!l1' ,\1"'''~~M!!!!UJ2 Rudi"Ii!!!!.kmL~wlyl1l l11'n"" I(~II~" IlW>U M pl> RPM WMMSOP K
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1..:"",<, 1("""",""""""H-AI'1.H !{11M WMMU~>H--1~.h ..
[~: Indent; left: 0.25", No bullets or
, numbeM9
[
FOl1lllltted: Indent: lelt: 0.25·, No bullets ~ numbering _
1F;,--..miibd;lnde'~t;' left;-O:2S-';-N~-~-I~; -1
numbenng .
White Mesa Mill -Standard Operating Procedures
SOP PBL-RP-I
Book 9: Radialion Protection Manual, Section J
Da~: HIl/IO Revision: DUSA-4,~~
Page 16 of 19
~, '"Isith lieu ,,, ~UI" III dl!'tFeY illl 11It!""if!o ~1It:l IA!,1If1! IHtlflll1 {lllitllllilHi !>IIII'" I'If UII}
~ ,,''''ScI''I II' .\lIow IIId lff<mi\lIli III .i<:ll~ ttl dtlu~ ffla{rill mj-".
1.4.5.4 Saftty Prtcautions
Follow laboratory guidelines when working with acids.
L-Utilize all appropriate PPE,
1.4,5.5 Sample Preparation Procedure
I. Compare sample numbering with bioassay result sheet 10 insure order and eliminate
discrepancies.
2. To aH15 ml clfllJril~ tuhe ndd I mL urins: ~ lmple, 200uL internal standard of 1.000
000 an,1 2(~ Nitric acid 10 make up volume (0 10 mL.seiRtillatleR ,·ials. 8611 S ",Is
instAlmeRt grade eenet!RIFah!d Rilrie aail:! 9:fId I ml een~RIF3letl perel'lloril> neiiJ
3. Maintaining sample order of left to right, front to back, lowest sample number to
highest sample number in the sel: a6e 5 mi lA 19 ml al SQRlpie Ie Ille 5eullillllilEln "iet
4. US\! vortl!X 10 mix II lhorouehly.Swir! Iht! Vial allEi plael.! 91l 1'101 platt!. a~
AlHillluiniRg 1111.4 aI~d -!04~ ~~. I--klf fl'I~ ~k& Ilt! ~ -Mt1Kkw. . ~ ({)
"flak tJnWft fm epp«t~ ~ '1etH' fJ'fit'" hi flt'!fl!hl\'l~i~ r!.a'ot' ur tli~l!~hall.
5. AnQlyze US;"l! procedure on the (CP-MS der;crihc.!l 1n.,l)l!clIqn 1.4.S.6.Caal: sampll!s
dawn 19 Jle~IIIf1Fie salls. If IheA! is any bf~WfH*}Ier-M1 in lflt! M~lfIple, rllpt!al
digl!Sttoll. II is impan 6ft1 Ihol 'Hel as!'1ing ef s8Rlp!e is eM!!)I!!l!! 18 ift51;1~ eltitlfl~
Ihe IIfOnil:llfl.
(j Phis!! IRe ~amp!l!s In e~'eR al 55Q"C fer 81leaSl 'l! hel:lF.
7 Rl!ma',ze samp~flHht!-6Yt!f};-alle~!:I add 19 ml af I % OF 2% Ailne aeiEl
Il:!al has Q.2% w!!lIi"!! a~nlla II;hH,;m~~
g. Heal tile sam (lIes Ie I:!ij!:esl salts
,. '~1ill. we \ttili:!! "p.Ylli.!cl..!!2..J!iUll~!I'tl,"~ta~~~I)!Ll_Lk,'o', ~.,n~~I.\&:~I.I .. AppJlJil1!I..'!!M],!.~tK. ~L,!:hlll''IIl,"r~_I .. ",.!'",~IRIIwlI"'''_~HIl);I'·". ~.'I,j,rJI)O"':~Sj>o.",;.~I...-...",.tJlI-R.diH1""'''''..-MllfWioIIIl1
1~"", ..... Il_ .... U~I-AI'I'I) IWM-WMMSI~~
(Formatted: No bullets or numbering, Tab ~
stop$: Not at 0.63" __
Formatted: Indl!llt: Left: 0", Han<;ling: 0.25',
Outline numbered + Level: 1 + Numbering
Style: 1, 2,), . + Start at: 1 + Alignment: left
+ A1i~ at: 0.13" + Tab lifter: 0.63" +
Indent at: 0.63", Tab stops: 0.2S", LiSt tab
Fonniltted: Indent: Left: 0", First lir1e: 0",
Tab stops: Not at 0.25"
Fonniltted: Indent: Left: 0", Hanging: 0.25",
Numbered + Level: 1 .. Numbering Style: 1, 2,
3, ... + Start at: 1 + AUgnment: ll!ft + Al~
at: O' + Tab after: I" + Indent lit: 1", Tllb
stop$: 0.25", list tab + NoUI 1"
Formatted: Indent: Left: 0", Hanging: 0.25",
Numbered + Level: 1 + Numbering Style: I, 2,
3, .• + Start at: 1 + Alignment: Left + Aligned
at: 0" + Tab after: 1" + Indent at: 1", Tab
stops: 0.25", List lab + Not at 1"
Formatted: Indent: Left: 0", Hanoing: 0.25",
Numbered + level: 1 + Numbering Style: 1,2,
3, ._ + Start at: 1 + Alignment: Left + Alignl!d
at: 0" + Tab after: 1" + Indent at; 1", Tab
~s~tops~·~,~O.=2~~,L=ist~ta~b~+~N~ot=a~t~1~" _______ ._
White Mesa MilI -Standard Operating Procedures
SOP PBL-RP-)
Book 9: Radiation Protection Manual. Seclion I
1.4.5.6 ICP·MS Procedure,
Date: 11)1110 Revision: DUSA·4-~~
Paae 17 of 19
Special considerations: Because of the .high salt content of the samples, it is necessary to
clean the skimmer and sampler cones after each use.
J. Tum the argon on at the tank and set the delivery pressure at 80 pounds peT square
inch (psi).
2. Tllrn on Ihe exhausl Inlland Ihl! Watl!r supply to the ICP-MS. The water supply has 10
hav\! a delivery pressure of 70 pSI, "Olav hi! necessnry (o changl! Ihe tillers on til<!
\VaICT supply in order 10 achieve ~ufficicnl woter supply prcssur<:l. The ICP MS will
nOI operate below Ihis prcssure.Th~ ICP MS 16 iAII eeAliAtl9t1S S19Rda¥ m9d~ Rl:!eaYSt!
il i~ Rt;'IOI!,;"Af)' IflltlllilllAin Q " ail"'''''II''' IllI! Ih~llft'lllf. 11l1f18\ Ie t:rIWA Ih .. :.IfIRdh~ AItltW
~~fMdt! ~ I~QN mtW<lft.
3. Turn on Ihe! compull!r. monitor and prinlerTheftl IIA! Iwe lurea \'alJtltlffl fltlfflf)~, Ihal
u~d 19 eefne \If) Ie sp~€! flRer 19 flpt!FIlliflg Ihe IGIl MS WIIIIt! wAIIIAg rer IRe
\lIlAlfls. PilI'S!! Ihl! illiarras!! 3ft!3 "'il~ erga" by pA!5smg-l-hll I aAEI 911I1eR~. TAt!
Qr~1I ligl .. \foi l! n llllt! till w~il.· .I:ll' a't!1I1I i31·lIf~"t~. II Ii a ¥t1I'tl 'tlt'A Itl pttr~~ tjl Iti\!,+
+t-ifftes.
4. OQ Lh.& .w!nduw ... d '~klop double-click Ihe ELAN icon.TlIAI eA 'I:le t!JlI:liUISI faA 8A€!
Ihs ~"III!!r SIIJlflly 10 IRe ICP MS. Tile wat"F stlflflly RiIS Ie ha'll! a dt!livtlry JlFeSSIiFe af
7Q psi. II may at! fleet!5SI1f)' Ie ehaRgd IRt! Hltt!F!' eA lilt! welt!F SUflfll)' IA 6Fder 16
lI~hil' ... t! 'ftlAitoi~fII .... ale' ~llflfll~' flF~~,,\II11' Til .. ICP M~ ~ ill 11111 lIpo:!FIlIt' tlC'I"' .... Ihi~
flft'~~lIre
C~cck Iht: cORdlliill!. 01 Jh£_!I!.nlp!1! introduclion s}slcm.TIIAl aA IRe [ellllllllt!r aAd
eAler IRt! SIlt!eIFa flFegFftffi.
6. Check Ihnllhc sllJTl1'le ubiu' 1![!ti tirutn lubiOl' II! d!!ll! from Ihe IlCn}luhic um [0 [he
~pnlY chumber are properly set up and 10 1l00d workin!! condition. 1l is recQmmttnckd
to use nl!w lube~ ~vel) da,J'.PA!ss Ihl! START blillaR 19 staR (hI! igRiliaA ~EjIlI!REI!.
TRI! igRiliEIil slep is 6Q ~eeIlEis. Al IQ seeon€!s lhe ·,'Aell~ fI\lfJlfI fer Ihe-tfllerfaet!
fMtA.S. "~~Mt~.fAA'" -RO+ ~. ItI.! ~ ...... I~ ........ ~,". '-' ~ ~
~i+tEHl:-
7. Place thl! carillaI)' lubin~ into a comainer of 2'~ Nllric acid solutfon.Aftt!F tRe plasma
igAile~. lilt! t!1t!elfBR ies ga lIIreuli!h II eRee" IEiali AYeicl en)' input 10 IJle eefJIfllfler
dUFin~ litis lime.
b..l.Y~-tM'>tl\!.'l1.wY"h"L II'! 1{.~Wl! .. n j'wl, ~'n"".!I!l71.1WI!Y; 11"".~"I~'i":rL6.cJ!1l.ill'M W~lMS()I'11 ~hllrJ/'.Ifil"",;knb .. "'IIl_..,.'IIII"llh,""" .• • .... mi\l/l~ ...... "'.kI<f""''''~<;''' · ... I+,"d.!'I1~.,I.-<""-J(.~i Ih .... II .. II-MMUI/I/Il'
1,;,:"l1"" K~n;.".'I I-i\I'f'I-1 Hl'M '~'M:>'~W H.,' Hlh"' ...
( ~~.tted: Body Text, Left, Indent: Left: ~
.( 1'ormattJed: Font: Bold
White Mesa Mill -Standard Operating Procedures
SOP PBL-RP-I
Dille: HJ.J/IO Revision: DUSA ~ ~~
Book 9: Radialion Proteclion Manual. Seclion 1 Page 180f 19
8. O,llen the instrumenl window, and thell click the Front Pa\leJ Tab,UIIElI!F Ihl!
illSIRlmeRI WillElBw ill Ihe gl!RllflllOF pal'llRll!ll!FS I\lFR Ihl! fl\lmfl en BREi Sill Illlllh!9Ylii!t!F
new Ie Ihe appFepriate (I,,*,IIRI tleh!FR'liReE! fiem pflltJia.,.s sel \If) 9f1eFalieRs.
9. On !he Imlll (lao!!1 tnb click vacuum Slim VIIIl!!, Ulilities. seleel !JIe SSM MBRBoeF
..... iRl:law. ~FeffI IRis windew. select Ihe lime seaR llial ~IQS IIFl!vie.,.sly Be!!R Mll Uf! fer
your 9f1eruhaR.
10. Whl!n the InSlrument is ready. click Pia. mn Stan.Uslllg Ihe lIl:Slfllmt!1I1 seUiR~s. IIdjllSI
(\IF 'lIt!Fify Ihallhe Rh liRe is aBoul1 X I g~ eeUAlS Clase aRE! ~il Sea II Mallllgef.
II. Aller the plasma IgOlle .. allow Ihe inslrumcnl In warm up for 45 minule~ . .yfltl«
MeitsuFe. ~l!ll!el Ql:lltlllilllli'Je IIlldlheR BiellRalysis.
12. To begin sample analYSIs, click Ihe sample tab. !lulld tbl! sample analYSIS Irsl and click
on analyze sample. After t!flleAlig Ihis ..... iRElaw liRtJer MrReliell. seleel SllIndamize
MetRad 811t! €ella\'! flr9lftplS. After 'IeFifyillJ!: sI8RtlIlFElitltltell • .. iHl:les 8Ft! elese Ie
fH\!'YtmJ!.. ~.al~. t>toMiA Mtlll~ itR~
13. Afler the lasl sample. aspi"'Ih! (he bl:lOk long enough 10 clem Ihe IrncdJt!t!ause al Ille
Illtllife ef lilt! samflh!. it is fleeessllf)' Ie aspirate 8 e18AI, iR helwt!!!R tlaeR SQl'Aflle. ,.UteF
5 19 7 salllflies. Ihe hIQAI, Rt:!eils 19 be aspiflllt:!1:i ref II slIflieieRI lime Ie sleaR Ihe sah
Inliltilip.
14. Allow Ihe pump \0 run long en ug.h wlthoul aqueous uptuke \0 VOIU all linl!s:ra ht:!IWI
&affifJ\tl-aflR~r-flf~-er-(l~iek-I~~KEHHlH~~leRI h:!A. side el Ihe
wlflt:lew, ~eeeffi Ille "Bille 8118 Hteve Ie Ille ReIn sample.
I S. Turn th~ 114me off and relax lipes on ol llumv.A!ler Ihe hlSI sample. ellll ' .... iRt!ew ElRd
aSfliFBle !"'e hlaRIE leRg eRe.,.!!:'" Ie cleaR Ihe liRes aAd ehaHtsers.
16. Aller 5 to 10 minutes. tum ol'fthe water SUVll I}' , exhaust Ian anu arggn .Alle"" IIII!
fltuUPI& filII leRg elletlgll wiIReUf-Mjue<Jus I:IJlIa*e-te.yeikll-~Jlt!5-illld cllaHtbers.
18, Ptlsk ihe STOP IHlllelHa 20 eeel, Ie the SHlfId~y-meae,
+9rAAer§ Ie IQ mil\tlltls HI~ en Ihe walef5uflflly. ~h81:1SI 18R alld llrgS"
All bioassay samples need to be analyzed Ihree (3) work.ing days from receipt in the
laboratory. Samples are extremely susceplible 10 contamination. Precautions should be
tak.en to minimize traffic and fugitive dUSI while samples are digesting.
l'S. Jl.J!lJ' ~~ylJ!, .. ~ 11'1 It:UJjU\!"D 1'"" M.lDu,OYi7 U..,n", l(o"ow,'!\"''I'I!.Arn!l !II'M W.\l~.lS!.!t.li.
~oshllf '/flnllwll<II ""'1!"'''lfflIIlo.'''''''flIl"rnl<.~HI~I"'''~(''l<krl~'''" •• ","! 1.,ld.;rm .. oI,.l<O I(.~""",,, ''''''-'M"",.lIm I,k,,, ... I',..,e",.,J);, ... U.JIrrl' Ht'M·WMM'lt)l<U l llo'!.tl,,,
i =~ Indent: ~ 0.25", NobIJlletsor
I'OnNttlled: Indent: Left: 0", Hanging: 0.25",
Numbered + Level: 1 + Numbering Style: 1,2,
3, .. + Start ~t: 1 + Ali9nmenl: Left + Aligned
at: 0" ... Tabatter: 0.5" + lndent~t: 0.5", Tab
stops: 0.25", List tab + Not at 0.5·
Formatlled: Body Text, Left, Indent: Left:
0.25'
White Mesa Mill -Standard Operating Procedures
SOP PBL-RP-I
Book 9: Radiation PrOiection Manual, Section 1
Date: Ig~/I0 Revision: DUSA4-j.~
Page 190fl9
"''',*'O..,lttiiIlIM1I~1!-;'''iIffi'4fl.hll+i.~111l'''P-Qllflf~~lfIftiil"*tJftet!!-'o\",4.'ilU:RHla"II""'iliMlI:lflflA-t~~'9~t!l1~1\ HAt'· wfiieh ~ ',*"",~II hI!!> ht:t!R
t:M~.
1.4.6 Reporting and Corrective Actions
As soon as the analytical results are received, they are entered in the logbook and the
entries are checked for correctness and completeness.
The lab report is returned to the Radiation Safety Department with results reported as
microgramslliter of uranium. The information must be placed in the individual
employee's exposure file and maintained as directed by the DRC.
The Radiation Safety Department is notified immediately of any sample with a
concentration greater than 35 micrograms/liter of uranium. Corrective actions will be
taken when the urinary uranium concentration falls within the limits listed in Table 1
(auached).
The Radiation Safety Department should compute the error on the control spiked samples
and advise the lab if the results are more than ± 30% of the known values. If any of the
results obtained for the quality assurance control samples are in error by a ± 30%, the
analysis must be repeated.
I.S IN-VIVO MONITORING
In-vivo body counting for lung burdens of U natural and U-235 will not be routinely
conducted, Monitoring will be conducted at the discretion of the RSO, samples may be
sent for a follow-up analysis for specific radionuclides in consultation with DUSA
management should potential exposure to an individual warrant.
1J;\,\!r1l ~I II' M4"'Tt:"nvUI",,~ U~ I\.~!,"" n """. ~1""\laIU!7 1 '\\'0:'; 11.<0"",1\.<;"", Arm' UI'M \\IMMSpl' K ~~nr 1/11111."<,, u ..... "'''''' fk._,~" .... _"VIl.\ ..... t;-It"'r/~)."",.,~""i.I ' • .w.:.iII, .. ol,.'IQ.R""i"'it,,, I, ... -M"""",~
1.k< .... ,lIr ........ V&"H-A,'I") ICI'~('\I"~,<;I.W M-l UX <I '
White Mesa Mill -Standard Operating Procedures
SOP PBL-RP-l
Book 9: Radiation Protection Manual, Section 1
1.0 RADIATION MONITORING -PERSONNEL
Date: 12/10 Revision: DUSA-5
Page 1 of 18
This section contains the following procedures for personnel radiation monitoring
including: (1) airborne particulates (2) alpha surveys (3) beta/gamma surveys and (4)
urinalysis surveys.
1.1 AIRBORNE PARTICULATES
Sampling for personnel exposure to airborne particulate radionuclides, other than for
radon progeny, will be done utilizing two distinct sampling protocols: (1) personnel
breathing zone samplers, and (2) ambient air high volume samplers. Specific standard
operating procedures for these two collection methods are described in Section 1.1.2 and
1.1.3 below.
1.1.1 Frequency
For work where there is the potential to cause airborne radiation doses to site personnel,
the frequency and type of air sampling to be conducted is determined from measured air
concentrations:
0.01 DAC -0.1 DAC Quarterly or monthly area air sampling and/or bioassay
measurements
> 0.1 DAC Continuous sampling is appropriate if concentrations are
likely to exceed 0.10 DAC averaged over 40 hours or
longer.
The RSO will determine the exact frequency of area air sampling, breathing zone
sampling and/or bioassay measurements and determine how many workers in a group of
workers performing similar jobs are to be equipped with breathing zone air samplers.
Higher airborne concentrations warrant more frequent use of area air samplers, bioassay
measurements, and breathing zone air samplers. Area air samplers may be used where
documentation exists showing the sample is equivalent to a breathing zone sample.
Breathing zone samples taken within one foot of the worker's head are considered
representative without further documentation. Breathing zone air samplers are preferred
under work conditions of higher airborne concentrations. Table 1.1.1-1 below, from
Regulatory Guide 8.25, provides additional guidance for the RSO in designing and
implementing air sampling programs for specific jobs.
C;\Users\jtischler\Desktop\Secti AppD RPM WMMSOP R-S .doc
White Mesa Mill -Standard Operating Procedures
SOP PBL-RP-1
Book 9: Radiation Protection Manual, Section 1
Date: 12110 Revision: DUSA-5
Page 2 of18
Table 1.1.1-1
Air Sampling Recommendations Based on Estimated Intakes and Airborne Concentrations
Worker's Estimated Estimated Airborne
Annual Intake as a
Fraction of ALI
< 0.1
>0.1
Any annual intake
Concentrations as a Air Sampling Recommendations
Fraction ofDAC
< 0.01 Air sampling is generally not necessary.
> 0.01
<0.3
> 0.3
>1
>5
However, monthly or quarterly grab samples or
some other measurement may be appropriate to
confirm that airborne levels are indeed low.
Some air sampling is appropriate. Intermittent or
grab samples are appropriate near the lower end
of the range. Continuous sampling is appropriate
if concentrations are likely to exceed 0.1 DAC
averaged over 40 hours or longer.
Monitoring of intake by air sampling or bioassay
is required by 10 CFR 20.1502(b).
A demonstration that the air samples are
representative of the breathing zone is appropriate
if (1) intakes of record will be based on air
sampling and (2) concentrations are likely to
exceed 0.3 DAC averaged over 40 hours (i.e.,
intake more than 12 DAC-hours in a week).
Air samples should be analyzed before work
resumes the next day when potential intakes may
exceed 40 DAC-hours in 1 week. When work is
done in shifts, results should be available before
the next shift ends. (Credit may be taken for
protection factors if a respiratory protection
program is in place.)
Continuous air monitoring should be provided if
there is a potential for intakes to exceed 40 DAC-
hours III 1 day. (Credit may be taken for
protection factors if a respiratory protection
program is in place.)
C:\Users\jtischler\Desktop\SectJ AppD RPM WMMSOP R-S.doc
White Mesa Mill-Standard Operating Procedures
SOP PBL~RP~ 1
Date: 1211 0 Revision: DUSA~5
Book 9: Radiation Protection Manual, Section 1 Page 3 of18
1.1.2 Breathing Zone Sampling
1.1.2.1 General
Breathing zone samplers (SKC pumps and accessory kits, or equivalent) are used to
determine airborne exposure to uranium while individuals are performing specific jobs.
The units consist of a portable low volume pump that attaches to the individuals belt,
tygon tubing and filter holder that is attached to the individual's lapel or shirt collar. The
unit monitors airborne uranium in a person's breathing zone. Pumps must be recharged
after 6 to 8 hours of use.
1.1.2.2 Applicability
Breathing zone samples are required:
• for all calciner maintenance activities,
• at least quarterly during routine operating and maintenance tasks on
representative individuals performing these tasks,
• when radiation work permits are issued in which airborne concentrations may
exceed 25% of 10CFR20 limits,
• weekly for yellowcake operations, or
• at the discretion of the RSO.
1.1.2.3 Procedure
The procedure for collecting a breathing zone sample is as follows:
1. Secure the breathing zone sampler, which has been charged and loaded with a filter
paper from the radiation department.
2. Secure the pump to the worker's belt and the filter holder to the shirt collar or lapel.
Try to secure pump tubing to minimize restriction of motion.
3. Tum pump on (record the time pump was turned on) and continue monitoring until
the work being monitored is completed and the worker no longer is in the exposure
area. Record the time at which the job is complete.
4. Return the pump and accessories to the RSO, who will remove the filter paper for
analysis. Be sure to indicate accurately the total time taken by the work being
monitored.
5. Analysis of filter samples will be performed using a sensitive alpha detector. The
procedure is as follows: (a) count a background sample for ten minutes; (b) divide the
C:\Users\jtischler\Desktop\Sectl AppD RPM WMMSOP R-S.doc
White Mesa Mill -Standard Operating Procedures
SOP PBL-RP-l
Book 9: Radiation Protection Manual, Section 1
Date: 12/10 Revision: DUSA-5
Page 4 of 18
background count by ten to obtain the background count rate in cpm; (c) Place the
breathing zone sample in the instrument and count the sample again for ten minutes;
(d) divide the sample count by ten to obtain the count rate in cpm; (e) subtract the
background count rate from the sample count rate; and, (f) record all data on the
Breathing Zone sampling analysis form (a copy of which is attached).
6. Record the total hours of exposure that are being assigned to the employee on the
Employee Exposure form, which is maintained in personnel folders. Be sure to
consider protection factors permitted by respirator use if the employee was also
wearing respiratory protection during the job.
7. The number of DAC hours assigned is calculated using the following formula:
DAC hours
of exposure
Measured air concentration x Total hours of exposure
(DAC)(PF)
where: DAC = Derived Air Concentration (for uranium; 10 CFR Part 20,
Appendix B)
PF = protection factor for respirator use. If no respiratory
protection was used PF = 1.
The measured air concentration must be in uCi/cc.
1.1.2.4 Calibration
Prior to use, calibration of the breathing zone samplers will be done using a calibration
method as described in Section 3.2.
1.1.2.5 Equipment -Breathing Zone Sampler
The equipment used for breathing zone samples consists of:
1. Personal sampling pumps
2. Gelman 37 mm Delrin filter holders, or equivalent
3. Gelman 37 mm type AlE glass fiber filters, or equivalent
4. Kurz Model 543 air mass flow meter, or equivalent
1.1.2.6 Data Record
Data maintained on file includes:
1. Time on and off for each sample pump.
2. Sampling location(s).
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White Mesa Mill -Standard Operating Procedures
SOP PBL-RP-1
Date: 12110 Revision: DUSA-5
Book 9: Radiation Protection Manual, Section 1 Page 5 of 18
3. Individual's name, identification number, etc.
4. Date and sample number.
5. Sample count rate.
1.1.2.7 Calculations
The airborne concentration in uCi/cc is equal to the sample count rate minus the
background count rate in cpm divided by the instrument alpha efficiency, the sample flow
rate in cc/minute, the sample time in minutes and a conversion factor converting dpm to
uCi.
The calculation is:
Equation Number 1:
Airborne concentration = (Count Rate)
(Time)( eft) ( conversion factor)(Flow Rate)
i.e. uCi = (cpm-Bkg) 1 uCi (1) (1)
cc (eft)(2.22x106dpm)(cc/min)(min)
where: eff= cpm/dpm for counting instruments
cpm = counts/min
dpm = disintegrations/min
conversion factor 1 uci = 2.22x106 dpm
Flow Rate = cc/min
Collection time = min
Once the airborne concentration has been calculated it is possible to calculate personnel
exposure in microcuries (uCi). Personnel exposure is determined for an individual who is
working in an area at a known air concentration (uCi/cc) for a given amount of time
(hours) breathing the area air at an assumed rate. The breathing rate for a standard person
(Handbook of Radiological Health) is 1.20 cubic meters per hour (m3/hr).
The calculation for personnel exposure is:
Equation Number 2:
Exposure uCi = (uCi/cc)(1.20m3/hr)(hours of exposure)(conversion rate)
where: uCi/cc = air concentration from Equation 1
1.20 m3/hr = breathing rate for standard man (lCRP)
C:\Users\jtischler\Desktop\Sectl AppD RPM WMMSOP R-S.doc
White Mesa Mill-Standard Operating Procedures
SOP PBL-RP-l
Book 9: Radiation Protection Manual, Section 1
hours of exposure = hours
conversion factor = 106cc/m3
Date: 12110 Revision: DUSA-5
Page 6 of 18
It is also possible to determine the percent or fraction of the Derived Air Concentration
(DAC) for a particular radionuclide using the information obtained from the exposure
calculation and dividing this value by the regulatory limit DAC listed in 10 CFR Part 20.
% DAC = Exposure in uCi/uCi limit 10 CFR Part 20
For the natural uranium (V-Nat) the DAC limits from 10 CFR Part 20 for insoluble Class
Y compounds are as follows:
1.1.2.8
• Weekly
• Quarterly
• Yearly
1.0 x 10-3 uCi/week
1.25 x 10-2 uCi/Qt
5.0 x 10-2 uCi/yr
ALARAIQuality Control
The RSO reviews each monitored result and initiates action if levels exceed 25% of 10
CFR 20 limits. At a minimum, ten percent (10%) of the air samples collected in a given
quarter will be recounted using the same instrument or using a different instrument and
these results will be compared to the original sample results. Deviations exceeding 30%
of the original sample results will be reviewed by the RSO and the samples will be
recounted again until the sample results are determined to be consistent. Additional QA
samples consisting of spiked air samples, duplicate samples and blank samples will be
submitted to the radiation department for counting. This will be based on ten percent
(10%) of the number of samples collected during a quarter. The sample results will be
compared to the spiked values, duplicate values, or blank (background) values of the
prepared sample. Deviations exceeding 30% of the determined spiked, duplicate or blank
value will be recounted. If no resolution of the deviation exceeding 30% is made the QA
samples preparation will be repeated. Periodic reviews by the RSO and the ALARA
audit committee will be made and documented to ensure quality maintenance and
ALARA control.
1.1.3 Airborne High Volume Sampling
Grab air sampling involves passing a representative sample of air through a filter paper
disc via an air pump for the purpose of determining the concentration of uranium in
breathing air at that location. Although the process is only measuring airborne
concentrations at a specific place and at a specific time, the results can often be used to
represent average concentration in a general area. A high volume sample pump will be
used for this purpose. Samples will be analyzed as per standard gross alpha analysis
procedures using a sensitive alpha detector.
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White Mesa Mill-Standard Operating Procedures
SOP PBL-RP-l
Book 9: Radiation Protection ·Manual, Section 1
1.1.3.1 Frequency and Locations
Date: 12/10 Revision: DUSA-5
Page 7 of 18
The following principles used for the collection of area grab samples must be considered
when collecting a sample in order to obtain a representative air concentration that workers
may be exposed to during their assigned work tasks.
1. The locations selected for sampling should be representative of exposures to
employees working in the area.
2. For special air sampling, the sampling period should represent the conditions during
the entire period of exposure. This may involve sampling during the entire exposure
period.
3. For routine sampling, the sampling period must be sufficient to ensure a minimum
flow rate of 40 liters per minute for at least 60 minutes.
4. Sample filters will be analyzed for gross alpha using a sensitive alpha detector.
5. Grab sampling procedures may be supplemented by use of Breathing Zone Samples
for special jobs or non-routine situations.
1.1.3.2 Sampling Equipment
Monitoring equipment will be capable of obtaining an air sample flow rate of at least 40
liters per minute for one hour or longer. Equipment utilized will be and Eberline RAS-l,
or a Scientific Industries Model H25004, or equivalent. Filter media will be of
appropriate micron pore diameter. Equipment is calibrated prior to each usage as per
Section 3.3 of this manual.
1.1.3.3 Sampling Procedure
Steps for collection of area airborne grab samples are as follows:
1. A high volume pump will be used for sample collection.
2. Check sample pump calibration.
3. Locate sampler at designated site. Insert a clean filter, using tweezers, into the filter
holder on the sampler. Do not contaminate the filter. Log start time and Mill
operating conditions at the site.
4. Collect a sample for a minimum of 60 minutes at a flow rate of 40 liters per minute.
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White Mesa Mill-Standard Operating Procedures
SOP PBL-RP-l
Book 9: Radiation Protection Manual, Section 1
Date: 12/10 Revision: DUSA-5
Page 8 of18
5. After sampling is completed, carefully remove the filter, using tweezers, from the
filter holder and place it in a clean glassine envelope, or in the plastic casing furnished
with the filter.
6. Log all sample data on the log sheet.
A. Sample location and number (also on the envelope).
B. Time on, time off and date.
C. Mill operating conditions at the site.
D. Sampler's initials.
7. Analyze for gross alpha
1.1.3.4 Calculations
Perform calculations as described in Section 1.1.2.7.
1.1.3.5 Records
Logs of all samples taken are filed in the RSO's files. Data are used to calculate radiation
exposures as described in Section 4.0.
Whenever grab sampling results indicate that concentrations in work locations exceed
25% of the applicable value in 10 CFR Part 20, Appendix B, time weighted exposures of
employees who have worked at these locations shall be computed. Calculations will
reveal an individual's exposure in DAC hours. This value shall be assigned to the worker
and logged onto the worker's "Employee Exposure to Airborne Radionuclides" form.
This form is in Section 4. Whenever special air sampling programs (as required for
cleanup, maintenance, decontamination incidents, etc.) reveal that an employee has been
exposed to airborne radioactive material, the calculated value shall also be entered on the
individual's exposure form.
1.1.3.6 Quality Assurance
Calibration checks on each air sampler, prior to field use, ensure accurate airflow
volumes. Use of tweezers and new filter storage containers minimizes contamination
potential. Field logging of data during sampling and logging of identifying data on
sampled filter containers minimizes sample transposition. Quality control samples will be
analyzed as described in Section 1.1.2.8
Review of data by the RSO and by the ALARA Audit committee further assures quality
maintenance.
C:\Users\jtischler\Desktop\SectJ AppD RPM WMMSOP R-S.doc
White Mesa Mill -Standard Operating Procedures
SOP PBL-RP-l
Book 9: Radiation Protection Manual, Section 1
1.2 ALPHA SURVEYS
1.2.1 Restricted Area
The Restricted Area is defined as:
Date: 12110 Revision: DUSA-5
Page 9 of18
1. The property area within the chain link fence surrounding the mill property and the
area enclosed to the north and east of the facility by the posted Restricted Area fence.
2. The active tailings and liquid waste disposal areas.
All personnel who enter the Restricted Area will monitor themselves each time they leave
the Restricted Area and at the end of their shift. The Radiation Safety Department will
review the monitoring information. All personnel exiting the Restricted Area must initial
a record of their monitoring activity.
1.2.2 Instrumentation
The instrumentation utilized for personnel alpha scanning is listed in Appendix 1 at the
end of this manual. Personnel alpha survey instruments are located at the exits from the
Restricted Area.
1.2.3 Monitoring Procedures
The monitoring procedure includes the following steps:
1. The alarm rate meter is adjusted within the range of 500 to 750 dpm/lOO cm2 to
ensure a margin of 250 dpm/100 cm2 due to the low efficiency of this
instrumentation.
2. An individual monitors himself by slowly passing the detector over their hands,
clothing and shoes, including the shoe bottoms, at a distance from the surface of
approximately ';4 inch. An area that is suspected of possessing any contamination (i.e.
hands, boots, visible spotting/stain on clothing etc.) should be carefully monitored by
placing the detector directly on the surface and note the measurement.
3. Should an alarm be set off indicating the presence of contamination, the individual
should:
a. Resurvey themselves to verifY the contamination.
b. If contamination is present the individual must wash the affected area and
again resurvey themselves to ensure the contamination has been removed.
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Book 9: Radiation Protection Manual, Section 1
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4. If the decontamination efforts by the individual are not successful, then the Radiation
Safety personnel will be contacted to assess the situation. Further decontamination
may be required.
5. If an individual's clothing cannot be successfully decontaminated, they must obtain
clothing from the warehouse to use and must launder the personal clothing in the
laundry room.
6. Individual surveys are to be logged and initialed.
7. Access to and from the Mill's Restricted Area by all Mill workers, contractors and
delivery personnel, other than Radiation, Safety and Environmental Staff, Senior
Laboratory personnel, Mill Management and Mill Supervisory personnel and others as
may be designated by the RSO, will be limited to one or more access points as may be
designated by the RSO from time to time.
8. A Radiation Technician will be positioned at each access point designated by the RSO
under paragraph 7 above during peak transition times, such as during breaks and at
the ends of shifts, to observe that each worker, contractor or delivery person is
performing a proper scan. This paragraph 8 will cease to apply to any such access
point if and when one or more automated full body scanners portals or the equivalent
are situated at the access point, which would require workers exiting at that location
to scan themselves by exiting through the portal, and the procedures in this Manual
are amended to incorporate the use and maintenance of such portal or portals.
1.2.4 Training
All employees will be trained on the proper scanning procedures and techniques.
1.2.5 Records
Log sheets will be collected daily and filed by the Radiation staff. Records will be
retained at the Mill. Contamination incidents will result in a written record, which is
maintained on file.
1.2.6 ~i~its/l\~l\Jlj\
Contamination limits for personnel scans are set at 1,000 dpm/lOO square centimeters.
Records will be reviewed by the RSO to maintain levels noted as low as reasonable
achievable.
1.2.7 Quality l\ssurance
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Book 9: Radiation Protection Manual, Section 1
Date: 12/10 Revision: DUSA-5
Page 11 of 18
A random check of an individual's scanning technique provides quality assurance of the
monitoring procedures. Daily function checks using calibrated sources assures
instrumentation performance. Periodic review by the RSO and the ALARA audit
committee document and ensure quality control and ALARA maintenance.
1.3 BETA-GAMMA SURVEYS
Site employees working within the Restricted Area will be required to wear a personal
monitoring device (such as a TLD, LUXEL badge or other NVLAP approved device
which has been approved by the RSO and the SERP) during their work period. The
personal monitoring devices are normally issued to each employee quarterly; however,
during pregnancy or if the radiological potential for exposure to an individual is
anticipated to be elevated and requires quick assessment the badges may be issued
monthly.
1.3.1 Monitoring Procedures
The monitoring procedures consist of:
1. Personnel issued personal monitoring devices will wear the device on the trunk
(torso) of the body. The personal monitoring device records beta/gamma radiation as
well as other forms of penetrating radiation such as x-rays. A personal monitoring
device is an exposure record of an individual's personal exposure to radiation while
on the job. Therefore, personal monitoring devices are to remain at the Mill and
stored on the assigned dosimeter storage boards. All exposure records obtained by a
personal monitoring device which are not consistent with the exposure rates of work
tasks or work location measurements made throughout the Mill will be evaluated by
the RSO. This evaluation will result in an investigation by the RSO and a written
explanation ofthe findings. These written records will be maintained at the Mill.
2. Personal monitoring devices will be issued at a minimum quarterly and will be
exchanged by the Radiation Safety Department. Missing or lost badges will be
reported to management.
3. Female employees that become pregnant and continue to work during the course of
their pregnancy will be placed on a monthly personal monitoring device exchange
during this period. NRC Regulation Guide 8.13 provides guidelines to be followed
during pregnancy and is made part of this procedure.
1.3.2 Records
The Radiation Safety Department will maintain all occupational exposure records in the
departmental files:
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Book 9: Radiation Protection Manual, Section 1
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1. Occupational exposure records are a part of an individual's health record and, as such,
will be considered private information.
2. An individual may examine hislher exposure record upon request.
3. An employee terminating hislher employment with Denison Mines (USA) Corp. may
request a copy of hislher occupational exposure records.
4. The Radiation Safety Department on the signature of the employee will request prior
occupational exposure records.
5. Occupational exposure records will be made available to authorized company or
regulatory personnel.
1.3.3 Quality Assurance
Periodic reviews by the RSO and the ALARA audit committee document and ensure
quality control and maintenance of conditions ALARA.
1.4 URINALYSIS SURVEYS
1.4.1 Frequency
Urinalyses will be performed on those employees that are a) exposed to airborne
yellowcake or involved in maintenance tasks during which yellowcake dust may be
produced, or b) routinely exposed to airborne uranium ore dust. Baseline urinalyses will
be performed prior to initial work assignments.
Urine samples are collected on a routine basis from mill employees as required in
Regulatory Guide 8.22. Urine samples will be collected from employees who have
worked in yellowcake packaging, yellowcake precipitation, grind area (SAG mill), ore
feed, sample plant, scale house, and the sample preparation room every two weeks during
production periods. Samples will be collected from all other employees monthly during
production periods. During non-production periods, bi-weekly samples will be collected
if individual exposures are expected to exceed 25% of the DAC value otherwise samples
will be collected from all employees quarterly. Non-routine urinalyses will usually be
performed on employees who have been working on assignments that require a Radiation
Work Permit, and always on any individual that may have been exposed to airborne
uranium or ore dust concentrations that exceed the 25% of the DAC level.
1.4.2 Specimen Collection
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Book 9: Radiation Protection Manual, Section 1
Date: 12110 Revision: DUSA-5
Page 13 of 18
Clean, disposable sample cups with lids will be provided to each employee that will be
required to submit a urine specimen. The containers will be picked up at the
administration building before the individual enters the Restricted Area.
The container, filled with specimen, will be returned to the bioassay laboratory prior to
reporting to work. The name of the employee and the date of collection will be indicated
on the specimen cup.
A valid sample must be collected at least 40 hours, but not more than 96 hours, after the
most recent occupancy of the employee's work area (after two days, but not more than
four days off).
The specimen should be collected prior to reporting to the individual's work location. To
prevent contamination, the hands should be carefully washed prior to voiding.
Under unusual circumstances where specimens cannot be collected in this manner, the
worker will shower immediately prior to voiding.
1.4.3 Sample Preparation
Equipment required:
• 15 ml disposable centrifuge tubes with lids
• 10 ml pipette
• 1 mL pipette
• 200 uL pipette
• 5 ul pipette
• 10 ul pipette
• Disposable tips for the above pipettes
• 1,000 ppm uranium solution
• Spiking solution -0.03 or 0.02 gIl of uranium in de-ionized water
After the specimens are received, they will be stored in a refrigerator until they are
prepared for analysis.
Sample preparation will be done in an area decontaminated to less than 25 dpm alpha
(removable) per 100 cm2 prior to preparation of samples. All of the equipment that is
used in sample preparation will be clean and maintained in such condition.
A log will be prepared and the following information will be kept for each urinalysis
performed:
Sample identification number
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White Mesa Mill -Standard Operating Procedures
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Book 9: Radiation Protection Manual, Section 1
Name of employee submitting the specimen
Date of sample collection
Date the sample was sent to the laboratory
Date the results were received
Results of the urinalysis in ug/l
Indication of any spike used in ugll
Date: 12110 Revision: DUSA-5
Page 14 of 18
The centrifuge tubes will be marked with a sample identification number. 10 milliliters
of urine will then be pipetted into the centrifuge tube using the pipette device. Or 1
milliliters of urine will then be pipette into the centrifuge tube using the pipette device
(To prevent contamination, a new tip must be used for each specimen.) After each step of
the procedure, the proper entry must be made in the logbook.
The samples that are to be spiked for quality assurance purposes will then be prepared.
The spikes will be introduced into the sample with 5 ul or 10 ul pipettes. A new tip must
be used with each spike. With the standard spike solution (0.03 gil of U), a 5 ul spike
will result in a 15 ug/l concentration for the 10 ml sample; the 10 ul spike will give 30
ugll). The proper entry must be made in the logbook for each sample spiked.
After preparation has been completed, the QA samples are securely packaged as soon as
practicable and sent to the contract laboratory for analysis.
The samples that are to be analyzed in-house will be placed in the chemistry laboratory's
refrigerator until the analysis can be completed. A copy of the in-house analytical
procedure is described in Section 1.4.7.6.
1.4.4 Quality Assurance
To assure reliability and reproducibility of results, at least 25% of the samples that are
submitted for analysis will be used for quality assurance purposes. These samples will
consist of spikes, duplicates, and blanks (samples collected from individuals known to
have no lung or systemic uranium burden).
Spiked samples will be prepared as stated under sample preparation of this procedure.
Duplicates will be identical samples of the same specimen and/or spikes of identical
concentrations.
To assure reliability of the in-house analytical procedure, 10% of the samples will be sent
to a contractor laboratory for analysis. These samples will contain quality assurance
items designed to provide intra-laboratory comparisons.
1.4.5 Analysis
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Book 9: Radiation Protection Manual, Section 1
Date: 1211 0 Revision: DUSA-5
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After the samples are collected as outlined in Guide 8.22, they are identified to the lab by
collection date and number. Urinalysis results must be completed and reported to the
Radiation Safety Department within seven days of the sample collection.
1.4.5.1 Equipment List
1. Specimen collection cups with disposable lids (VWR No. 15708-711 or equivalent)
2. Screw cap, disposable, graduated 15 ml centrifuge tubes (Coming No. 25310 or
equivalent)
3. Micro-pipettes 1 each 5,5 each 10 microliters (Oxford Model 7000 or equivalent)
4. Adjustable Finnpipette each 1,000 uL, 200 uL and 5 mL
5. Disposable micro-pipette tips for micro-pipettes (Oxford No. 910A or equivalent)
6. Fume Hood
7. Ultrasonic Cleaner
8. PE-SCIEX ELAN DRC II AXIAL FIELD TECHNOLOGY ICP-MS (or equivalent)
9. Polyscience Water Circulator (or equivalent)
10. Perkin-Elmer AS-I0 Auto Sampler (or equivalent)
11. Thermo Scientific Vortex mixtures (or equivalent)
1.4.5.2 Reagent List
1. 1 % to 2% Nitric Acid
2. Concentrated Nitric Acid
3. 1,000 ug/ml Uranium Stock Solution, certified vendor prepared
4. Dilutions of the above stock solution, replaced bi-annually. Used for QAlQC.
5. Appropriate Cleaning Solution for Ultrasonic Cleaner
6. 1,000 ug/ml Uranium Stock Solution, purchased from certified vendor to use as
calibration standard at different dilutions
Ensure that all reagents used are within their expiration dates listed on each reagent
package, if applicable.
1.4.5.3 Premise
A portion of urine 1S diluted with 2% Nitric acid solution, mixed thoroughly and
analyzed.
1.4.5.4 Safety Precautions
1 Follow laboratory guidelines when working with acids.
2. Utilize all appropriate PPE.
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Book 9: Radiation Protection Manual, Section 1 Page 16 of 18
1.4.5.5 Sample Preparation Procedure
1. Compare sample numbering with bioassay result sheet to insure order and eliminate
discrepancies.
2. To 15 ml centrifuge tube add 1 mL urine sample, 200uL internal standard of 1,000
ppb and 2% Nitric acid to make up volume to 10 mL.
3. Maintaining sample order of left to right, front to back, lowest sample number to
highest sample number in the set.
4. Use vortex to mix it thoroughly.
5. Analyze using procedure on the rCP-MS described in section 1.4.5.6.
1.4.5.6 ICP-MS Procedures
Special considerations: Because of the high salt content of the samples, it is necessary to
clean the skimmer and sampler cones after each use.
1. Tum the argon on at the tank and set the delivery pressure at 80 pounds per square
inch (psi).
2. Tum on the exhaust fan and the water supply to the rCP-MS. The water supply has to
have a delivery pressure of 70 psi. It may be necessary to change the filters on the
water supply in order to achieve sufficient water supply pressure. The rCP-MS will
not operate below this pressure.
3. Tum on the computer, monitor and printer.
4. On the windows desktop, double-click the ELAN icon.
5. Check the condition of the sample introduction system.
6. Check that the sample tubing and drain tubing leading from the peristaltic pump to the
spray chamber are properly set up and in good working condition. It is recommended
to use new tubes every day.
7. Place the capillary tubing into a container of 2% Nitric acid solution.
8. Open the instrument window, and then click the Front Panel Tab.
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Book 9: Radiation Protection Manual, Section 1 Page 17 of 18
9. On the front panel tab click vacuum start.
10. When the instrument is ready, click Plasma Start.
11. After the plasma ignites, allow the instrument to warm up for 45 minutes.
12. To begin sample analysis, click the sample tab, build the sample analysis list and click
on analyze sample.
13. After the last sample, aspirate the blank long enough to clean the lines.
14. Allow the pump to run long enough without aqueous uptake to void all lines.
15. Turn the flame off and relax lines off of pump.
16. After 5 to 10 minutes, tum off the water supply, exhaust fan and argon.
All bioassay samples need to be analyzed three (3) working days from receipt in the
laboratory. Samples are extremely susceptible to contamination. Precautions should be
taken to minimize traffic and fugitive dust while samples are digesting.
1.4.6 Reporting and Corrective Actions
As soon as the analytical results are received, they are entered in the logbook and the
entries are checked for correctness and completeness.
The lab report is returned to the Radiation Safety Department with results reported as
micrograms/liter of uranium. The information must be placed in the individual
employee's exposure file and maintained as directed by the DRC.
The Radiation Safety Department is notified immediately of any sample with a
concentration greater than 35 micrograms/liter of uranium. Corrective actions will be
taken when the urinary uranium concentration falls within the limits listed in Table 1
(attached).
The Radiation Safety Department should compute the error on the control spiked samples
and advise the lab if the results are more than ± 30% of the known values. If any of the
results obtained for the quality assurance control samples are in error by a ± 30%, the
analysis must be repeated.
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Book 9: Radiation Protection Manual, Section 1
1.5 IN-VIVO MONITORING
Date: 12/10 Revision: DUSA-5
Page 18 of18
In-vivo body counting for lung burdens of U-natural and U-235 will not be routinely
conducted. Monitoring will be conducted at the discretion of the RSO. samples may be
sent for a follow-up analysis for specific radionuclides in consultation with DUSA
management should potential exposure to an individual warrant.
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ATTACHMENT 2
8
White Mesa Mill -Standard Operating Procedures
SOP-PBL-RP-3
Date: 08/09 Revision: DUSA-3
Book: Radiation Protection Manual, Section 3 Page 1 of 14
3.0 EQUIPMENT/CALIBRA TION
All radiation detection instruments used at the Mill are sent to a qualified independent
laboratory for calibration every six months. If necessary, Radiation Safety Staff can use
the procedures outlined below to verify calibration.
3.1 CounterslDetectors
3.1.1 General
All radiation detectors require determination of detector optimal voltage performance or
plateau operating point. The graph of voltage applied to a detector versus detector
response is referred to as a plateau curve. The plateau curve typically has two rapidly
sloping sections and a stable, flat region. The optimal operating point is typically located
at the beginning of the flat, or flatter, section of the graph. The plateau curve is specific
for a particular detector and its accompanying readout, or measuring meter, and may vary
over time depending upon electronic component condition.
The equipment used to determine detector plateau curves includes:
1. Appropriate radiation sources
2. Electrostatic voltmeter
3. Radiation detecting instrument
4. Graph paper
5. Manufacturer's technical manual
The procedure is:
1. Ensure instrument batteries are fresh or fully charged, if applicable.
2. Tum the instrument on.
3. Adjust the instrument voltage control starting at voltage of 600 using electrostatic
voltmeter to monitor voltage setting.
4. Expose detector to a radiation source applicable to the type of detector and in the
appropriate setting.
5. Record voltage and instrument response for each adjustment of voltage applied;
increments of 50 volts are adequate.
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SOP-PBL-RP-3
Book: Radiation Protection Manual, Section 3
Date: 08/09 Revision: DUSA-3
Page 2 of 14
6. Repeat steps 4 and 5 until instrument response rapidly increases versus voltage level.
At this point, the detector is approaching potential differentials across the electrode
that may damage the detector.
7. Graph instrument response versus voltage applied.
8. Set equipment high voltage control to the optimum operating point. Record on graph
voltage selected.
9. Retain graph with calibration records.
3.1.2 Function Checks
Calibration function checks are required prior to use of radiation detection instruments
used at the Mill for the purpose of verifying that the instruments are operating at the same
efficiency as when they were calibrated by the calibration laboratory (Le., within +1-10%).
Function checks are also used for verifying repeatability, reliability, and comparability of
an instrument's measurements from one period to another. By performing function
checks for extended time periods, or on a larger sample size, these goals are met.
Function checks involve two basic elements:
(1) calibration laboratory efficiency is compared to the instrument's efficiency on the
date of the function check; and
(2) the function check is verified with a check source having similar isotopic
composition as the one that was used by the calibration laboratory to calibrate the
instrument.
Function checks are made for all types of radiation survey instruments. The basic
principle in performing a function check is measuring the radiation field using a survey
instrument against a known amount of radiation from a calibrated source. These
measurements are made for the specific type of radiation occurring. For example, when
performing a beta/gamma survey, the instrument function check is performed using a
beta/gamma check source, such as a (SrY)-90. When performing an alpha survey, use an
alpha check source, such as Th-230 or Pu-239 for performing the function check.
Function checks are documented on the Calibration Check Forms (see Attachment A for
copies of forms to be used) for each specific instrument. They will be maintained in the
instrument's' calibration and maintenance file.
A number of radiation detection instruments are used at the Mill. An Instrument Users
Manual for each instrument is maintained in the calibration files, together with calibration
documentation. The Users Manuals are to be considered the primary reference for
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Book: Radiation Protection Manual, Section 3
Date: 08/09 Revision: DUSA-3
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operating a particular instrument. This Standard Operating Procedure (SOP) is not
intended to replace the Users Manual, but rather to supplement the Manual by providing
steps to be performed for function checks. Before operating an instrument, personnel
should read the Users Manual and become familiar with the instrument's operation,
capabilities, and special features. Personnel will also receive on the job training on each
instrument.
3.1.3 Alpha Monitors
Alpha particles travel very short distances in the air due to their high ionization ability -
typically Y4 to ~ inch. Due to this limitation, alpha monitoring must be done at a distance
of Y4 inch or less between the detector face and the source. Alpha monitoring, to be
consistent, requires ensuring a consistent distance be utilized between the detector face
and the source. Alpha detectors read out in counts per minute (cpm). A correlation
relationship, known as the efficiency factor, between the meter response and the actual
disintegration rate of the source is used to determine actual calibration of the meter.
Radioactivity is measured in curies (Ci), which, by definition, is 3.7 x 1010 disintegrations
per second (dps), or 2.2 X 1012 disintegrations per minute (dpm). Another measurement
unit is the Becquerel, or one dps. Alpha radiation is usually monitored as dpm, per
surface area measured.
Radiation survey equipment used at the Mill for alpha surveys are listed in Appendices 1
and 2.
3.1.3.1 Calibration and Function Check Frequency
The frequency of calibration is specified in individual instrument user manuals and
manufacturer's specifications.
During production periods, the following frequencies are observed for calibration and
function checks of radiation detection instruments:
Calibration Function
~ Freguency Checks
l. Employee scans 6 month 5 days/week
2. Radon progeny 6 month each use
3. Respirator checks 6 month each use
4. Area fixed scans 6 month Daily or each use
5. Area wipe scans 6 month Daily or each use
During non-production periods, the following frequencies are observed:
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White Mesa Mill-Standard Operating Procedures
SOP-PBL-RP-3
Book: Radiation Protection Manual, Section 3
~
1. Employee scans
2. Radon progeny
3. Respirator checks
4. Area fixed scans
5. Area wipe scans
Calibration
Frequency
6 month
6 month
6 month
6 month
6 month
Date: 08/09 Revision: DUSA-3
Function
Checks
bi-monthly
each use
each use
Daily or each use
Daily or each use
Page 4 of14
3.1.3.2 Function Check Procedures -Alpha Counters and Scaler Instruments
The following steps will be used for function checks for alpha counters and alpha scaler
instruments.
1. Tum the instrument on and place a calibrated alpha check source in the detector
holder on or the face of the detector.
2. Count the source for 1 minute and record this value in cpm.
3. Repeat step 2 four more times.
4. Average the five readings and divide the average in cpm by the known activity on the
alpha source. This is the efficiency of the instrument and detector.
5. Compare this efficiency with the efficiency obtained from the calibration lab. If the
efficiency comparison is within ± 1 0% deviation the instrument needs is calibrated if
not the instrument needs to be recalibrated.
6. If this efficiency comparison is within ±10% deviation the instrument is in calibration.
7. Proceed with monitoring activities.
3.1.3.4 Calibration Procedures
All radiation detection instruments used at the Mill are sent to a qualified offsite
laboratory every six months for calibration. However, if additional onsite calibration is
required the calibration procedures are:
1. Set the detector high voltage at the prIor determined operating point usmg an
electrostatic voltmeter.
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White Mesa Mill-Standard Operating Procedures
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Date: 08/09 Revision: DUSA-3
Book: Radiation Protection Manual, Section 3 Page 5 ofl4
2. For counter/scalers (radon progeny/wipes), close the detector, without source present,
obtain a reading for a set time. This is a background reading.
3. Place a calibrated source for the type of radiation being measured in the source holder
and obtain reading.
4. Observe the counts per minute for both the background and the source.
5. Subtract the cpm value of background from the cpm value of the source to obtain the
netcpm.
6. Divide the net cpm value by the known dpm of the source. This is the percentage
efficiency of the instrument system for this energy source.
7. By dividing 100 by this efficiency, an efficiency factor is obtained.
8. Dpm equals the cpm divided by the efficiency ofthe instrument detector system:
Note: 1 curie = 2.22 E + 12 dpm
1 microcurie = 2.22 E + 6 dpm
1 picocurie = 2.22 dpm
3.1.4 Beta-gamma Monitors
Equipment utilized for beta-gamma monitoring is listed in Appendices 1 and 2.
3.1.4.1 Function Check Procedure
The following steps will be used for function checks on beta/gamma instruments:
1. Tum the instrument on and place the calibrated beta/gamma (SR-Y)-90 check source
on the face ofthe detector.
2. Let the reading stabilize to a constant value.
3. Record this value in cpm.
4. Divide this value by the known activity on the check source. This is the efficiency of
the instrument and detector.
5. Compare this efficiency to the efficiency obtained from the calibration laboratory. If
the efficiency comparison is within ±10% deviation the instrument needs is calibrated
if not the instrument needs to be recalibrated.
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White Mesa Mill -Standard Operating Procedures
SOP-PBL-RP-3
Book: Radiation Protection Manual, Section 3
Date: 08/09 Revision: DUSA-3
Page 6 of 14
6. If this efficiency comparison is within ± 1 0% deviation the instrument is in calibration.
7. Proceed with monitoring activities.
3.1.4.2 Calibration
All beta-gamma survey instruments are sent out every six months for calibration.
Additional calibration, if necessary, may be performed on site using techniques described
in Reg. Guide 8.30, Appendix C -Beta Calibration of Survey Instruments for calibration
performed by a qualified calibration laboratory using the indicated source as listed in
Appendix 2.
3.1.5 Gamma Monitors
Instruments for gamma measurements are listed in Appendix 1.
3.1.5.1 Calibration
Independent calibration service laboratories perform calibration every six months.
Meters are calibrated to Cesium-137 or other radioisotopes as suggested by the calibration
laboratory or manufacturer. Most calibration service laboratories calibrate Beta/Gamma
instruments electronically in accordance with their standard calibration procedures.
However, electronic calibration basically consists of the steps described below:
1. Connect survey instrument to be calibrated to the model 500.
2. Turn both instruments on.
3. Record high voltage reading on model 500.
4. Set cpm and the range multiplier on the model 500 to the desired meter deflection.
The model 500 frequency controls consist of the three-digit readout, range selector,
coarse tuning know, and the fine tuning knob. The three-digit readout is in cpm times
the frequency multiplier.
5. Calibrating survey instruments in cpm:
A. Set model 500 frequency to value that will provide a % meter deflection on the
survey instrument's highest count scale. Set pulse height/amplitude to twice
instrument input sensitivity.
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White Mesa Mill -Standard Operating Procedures
SOP-PBL-RP-3
Book: Radiation Protection Manual, Section 3
Date: 08/09 Revision: DUSA-3
Page 7 of14
B. Adjust the range calibration potentiometer on the survey meter to provide correct
reading record.
C. De-code model 500 frequency to next lower value; then do the same for the
survey instrument.
D. Adjust the range calibration potentiometer for correct reading on survey
instrument. Record readings.
E. Repeat process until all ranges have been calibrated at % meter deflection. Record
readings.
F. Return to highest count scale on survey meter.
G. Set model 500 for 'l4 scale deflection readings.
H. Survey instrument should read within ± 10% of model 500 frequency. Record
readings.
1) If readings are outside of the tolerance, re-calibrate for % meter deflection.
2) Tap instrument meter lightly to check for sticky meter. Meter tolerance is
± 3% from the initial readings to the final reading.
1. Decode M 500 to next lower scale. Check survey instruments for 'l4 scale reading.
Record.
6. Record input sensitivity.
A. Select the most sensitive amplitude range 0-5 mv on the model 500.
B. Observe meter on survey instrument.
C. Increase pulse amplitude, switching to next higher range, if necessary, until the
rate meter indicates a stable reading (i.e., further increase of pulse amplitude does
not cause an increase in meter reading). Now, decrease pulse height until the
survey instrument meter reading drops 15 ± 5%. Record this pulse height as the
instrument sensitivity.
D. If your instrument has a gain or threshold control to set instrument sensitivity, set
pulse height on the model 500 to desired sensitivity level. Now adjust your
instrument threshold or gain control until the rate meter reading is within 85 ± 5%
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White Mesa Mill -Standard Operating Procedures
SOP-PBL-RP-3
Book: Radiation Protection Manual, Section 3
Date: 08/09 Revision: DUSA-3
Page 8 of14
of its stable reading value (see step C). Record the pulse height as instrument
sensitivity.
7. Calibrating survey instrument to cps.
A. Set frequency in model 500. Divide model 500 readings by 60 to convert to counts
per second.
B. Repeat calibration steps as in item 5 above.
3.1.5.2 Frequency of Calibration
If electronic calibration is performed using the above method by the Radiation Safety
Department, the model 500 pulse generator will be sent out for calibration on an annual
basis.
3.2 PERSONNEL AIR SAMPLERS
The calibration procedure for personnel air samplers involves primary and secondary
calibration procedures. Samplers will be calibrated prior to each use by either of two
methodologies: bubble tube, electronic calibration or mass flow determinations. Air
samplers may be calibrated to standard air conditions.
3.2.1 Bubble Tube Calibration Method
The Bubble Tube Calibration Method is a primary calibration method and does not
require corrections to or from standard conditions for temperature and pressure. Personal
air samplers are calibrated for the flow rate for the sampling being performed, typically 2-
4 liters per minute.
The equipment utilized is as follows:
1. Burette -1,000 ml capacity, 10 ml divisions
2. Support, iron, rectangular base, with rod
3. Burette clamps - 2
4. Soap solution, dish
5. Tubing, Gelman filter holder, filter media (0.8 micron glass fiber Gelman type AlE)
6. Stopwatch
7. Small screwdriver
8. Sample pump
The procedures utilized are:
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White Mesa Mill -Standard Operating Procedures
SOP-PBL-RP-3
Book: Radiation Protection Manual, Section 3
Date: 08/09 Revision: DUSA-3
Page 9 of14
1. Assemble a filter train -place a filter in an in-line filter. Attach two lengths of tubing
to each connector of the in-line filter holder.
2. Make sure the Burette is clean. Clamp the 1,000 ml Burette upside down on the ring
stand with the Burette clamps.
3. Attach the pump to be calibrated to one end of the filter train, connect the other end of
the filter train to the small end of the 1,000 ml Burette, as per Figure 1.
4. Check all tubing connections for air tightness.
5. Pour approximately 11 inch (12 mm) of soap solution into the dish.
6. Start the pump.
7. Raise the dish up under the Burette opening, and then immediately lower the dish.
This should cause a film of soap to form over the Burette opening (i.e., a bubble).
Repeat this procedure until the film (bubble) will travel up the inverted Burette the
length of the graduation marks on the Burette without breaking.
8. When the film (bubble) has wetted the Burette inside and will travel the entire length
of the graduated area of the Burette, proceed with the actual calibration run.
9. Quickly form three bubbles and start the stopwatch when the middle bubble is at the
bottom graduation line (actually the 1,000 ml mark, but for purposes here, it will be
called the "zero" line).
10. Time the travel of the bubble from the zero line to the top line of the graduated
distance (0 ml). Since the capacity of the Burette is 1,000 ml (1.0 liter), then the
volume of air that is displaced above the bubble (i.e., needed to raise the bubble) is
1.0 liter. Stopping the stopwatch at the top mark is the time elapsed for the pump to
accomplish this. The rate of rise of the bubble through the apparatus is the flow rate
of air being pulled by the pump.
11. Increase or decrease the pump collection rate by adjusting the appropriate screw or
knob designed for this purpose.
12. Set the pump flow collection rate to the desired valued usually between 2 and 4 liters
per minute for low volume collection pumps and between 30 and 80 liters per minute
for high volume collection pumps.
3.2.2 Mass Flow Method
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White Mesa Mill -Standard Operating Procedures
SOP-PBL-RP-3
Date: 08/09 Revision: DUSA-3
Book: Radiation Protection Manual, Section 3 Page 10 of 14
Mass flow meters are manufactured equipment designed to measure air collection flow
rates for a variety of purposes. Mass flow meters may be subject to temperature and
pressure corrections of air movement depending on whether they are
calibrated/manufactured for standard conditions.
Utilizing an air mass flow meter, traceable to NBS, the airflow rate of pumps can be
quickly adjusted to correct standard flow rate conditions. However, the mass flow meter
must be calibrated annually using a primary calibration method.
The equipment consists of the following:
1. Kurz air mass flow model 543 or equivalent
2. Suitable filter head adapter connections
3. Filter heads with filter media
4. Pump to be calibrated
Note: The meter is calibrated directly in standard air conditions -25° c., 29.82" Hg..
The procedures utilized are:
1. Ensure pump batteries are fully charged.
2. Ensure flow meter batteries are fully charged.
3. Assemble filter train.
4. Connect (with a suitable adapter) the Kurz probe onto the filter train. Ensure an
airtight seal with tape, ifnecessary.
5. Set the meter function switch to the highest range: 40 std liters per minute.
6. Tum the pump on.
7. Select appropriate range on the meter. (Do not allow meter needle to be forcibly
pegged.)
8. Adjust the pump flow rate as necessary to desired flow rate. Allow the meter to
stabilize before adjustment of the pump.
9. Meter reads directly in standard air conditions, correcting for temperature and
barometric pressure.
Pump is now calibrated. Low volume pumps are set at 2 to 4 Ipm.
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White Mesa Mill-Standard Operating Procedures
SOP-PBL-RP-3
Date: 08/09 Revision: DUSA-3
Book: Radiation Protection Manual, Section 3 Page 11 of 14
3.2.3 Electronic Calibration Method
The electronic primary gas flow calibration is the primary calibration method and does
not require corrections to or from standards conditions for temperature and pressure.
Personal air samplers are calibrated for the flow rate for the sampling being performed
typically 2 - 4 liters per minute.
The equipment utilized is as follows:
1. UltraFlo Primary Gas Flow Calibrator, or equivalent
2. Soap solution
3. Tubing
4. Small screwdriver
5. Sample pump
The procedure proceeds as follows:
1. Remove the two nipples on the back of the UltraFlo Primary Gas Flow Calibrator.
2. Attach the connection tubing from the top nipple to the sample pump.
3. Tum calibrator on.
4. Tum sample pump on.
5. Press the plunger style button on top of the soap dispensing portion ofthe device.
6. Write down the digital reading from the calibrator device.
7. Repeat steps 5 and 6 three times.
8. Take an average of the three readings.
9. If the sample pump requires adjustment, take the screwdriver and adjust the set
screw on the face of the sample pump and then repeat steps 5 through 7.
10. After the sample pump is calibrated, document the calibration on the Breathing
Zone/Radon Calibration Sheet, in the Radiation department.
11. Replace nipple caps on the back of the calibrator.
3.3 AREA AIR SAMPLERS
The calibration procedure for area air samplers involves one of the following procedures;
Kurz Mass Flow, Wet Test Gas Meter or Bubble Tube Method.
3.3.1 Kurz Mass Flow Method
Repeat procedures discussed in 3.2.2 -except -airflow rate is adjusted to 40 slpm and
samplers utilized are:
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White Mesa Mill-Standard Operating Procedures
SOP-PBL-RP-3
Book: Radiation Protection Manual, Section 3
1. Eberline RAS-l
2. Scientific Industries Model H25004
3. Equivalent
3.3.2 Wet Test Gas Meter Method
Date: 08/09 Revision: DUSA-3
Page 12 of 14
The wet test gas meter method utilizes a Precision Scientific wet test meter rated at one
cubic foot per revolution of the main dial. This method is used to calibrate the Kurz air
mass flow meter in addition to direct calibration of the area air samplers.
The procedures are:
1. Attached coupling to sampler filter assembly; secure it with tape.
2. Connect wet test meter hose to coupling.
3. Check water level of wet test meter. The needle should be on slightly above the water
level.
4. Check the thermometer temperature of the wet test meter. Record this on the
calibration sheet. Assume that the wet and dry bulb temperatures are the same.
5. Tum on the sampler. Check the west test meter's manometer reading. This reading is
obtained by adding the left and right column values. (A typical reading might be .3).
Log these values for each ball height on the "Static pressure ... H20" column.
6. For the following sampler approximate settings, pull one cubic foot of air through the
wet test meter and record the time (in seconds) for each: 20, 30,40, and 50 lpm.
Sampler Calibration Procedures -Calculations and Equations
1. To convert the static pressure (of the manometer attached to the wet test meter) from
inches of water to inches of mercury, divide the number of inches to water by 13.6.
Example: 0.4/13.6-0.02941176" Hg
2. To compute the actual flow rate ("Q rate act. lpm"), first divide the number of cubic
feet by the number of seconds. Example: 1 ft.3/90 sec = .01111 ft.3/awx. Convert
the cubic feet to liters. The conversion factor is 28.317. Example: .01111 ft.3/sec x
28.317 L ft.3 = .3146 Llsec. Multiply this by 60 to convert from seconds to minutes.
Example: .3146 LIsee x 60 sec = 1888 LIm or 18.88Ipm.
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White Mesa Mill -Standard Operating Procedures
SOP-PBL-RP-3
Book: Radiation Protection Manual, Section 3
Date: 08/09 Revision: DUSA-3
Page 13 of 14
3. Using the "Vapor Pressures of Water" chart, find the vapor pressure inside the wet
test meter by matching the wet bulb temperature with the corresponding vapor
pressure. This number is the vapor pressure at the standard wet bulb (Pvpstw).
4. Find the vapor pressure at dewpoint using this formula: Pv dewpoint = Pvpstw =
0.0003613 (td-tw) Bp (Where +d = dry bulb temp; tw = wet bulb temp; bp =
barometric pressure in inches of mercury.) Assume that the dry bulb temperature
and the wet bulb temperature are the same, so the difference between them will
always be zero. Thus, Pv dewpoint will equal Pvpstw.
5. Determine the actual air density (D act) with this formula:
D act = 1.327
td + 459.67 [(Pg-Sp) -0.378 (Pv dewpoint)]
(Where td -dry bulb temp in degrees F.; Bp = barometric pressure in inches of
mercury; Sp = static pressure of wet test meter in inches of mercury.)
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White Mesa Mill -Standard Operating Procedures
SOP-PBL-RP-3
Date: 08/09 Revision: DUSA-3
Book: Radiation Protection Manual, Section 3
Example:
D act = 1.327
70.5 + 459.67
= 1.327
530.17
[(24,8031 -0.02941176) -0.378 (.875)]
(24,773688 -0.33075)
= (0.00250297) (24.442938)
D act = 0.06117996
Log this in "Air Density Ibs/ft3" column of log sheet.
Page 14 of 14
6. Find the flow rate of the sampler at standard conditions (Q std) using this formula:
Q std = Q act D act
D std
(Where D std = .075 Ibs/ft3)
(i.e., Q std = 18.88 (0.06117996)
0.075
= 18.88 (0.8157328)
15.40
Q std = 15.40 (write this down for each position in the Q 0.075 column)
3.3.3 Bubble Tube Method
Refer to Section 3.2.1 to perform this method.
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White Mesa Mill -Standard Operating Procedures
SOP-PBL-RP-3
Date: 12110 Revision: DUSA-4
Book: Radiation Protection Manual, Section 3 Page 1 of 14
3.0 EQUIPMENT/CALIBRATION
All radiation detection instruments used at the Mill are sent to a qualified independent
laboratory for calibration every six months. If necessary, Radiation Safety Staff can use
the procedures outlined below to verify calibration.
3.1 CounterslDetectors
3.1.1 General
All radiation detectors require determination of detector optimal voltage performance or
plateau operating point. The graph of voltage applied to a detector versus detector
response is referred to as a plateau curve. The plateau curve typically has two rapidly
sloping sections and a stable, flat region. The optimal operating point is typically located
at the beginning of the flat, or flatter, section of the graph. The plateau curve is specific
for a particular detector and its accompanying readout, or measuring meter, and may vary
over time depending upon electronic component condition.
The equipment used to determine detector plateau curves includes:
1. Appropriate radiation sources
2. Electrostatic voltmeter
3. Radiation detecting instrument
4. Graph paper
5. Manufacturer's technical manual
The procedure is:
1. Ensure instrument batteries are fresh or fully charged, if applicable.
2. Tum the instrument on.
3. Adjust the instrument voltage control starting at voltage of 600 using electrostatic
voltmeter to monitor voltage setting.
4. Expose detector to a radiation source applicable to the type of detector and in the
appropriate setting.
5. Record voltage and instrument response for each adjustment of voltage applied;
increments of 50 volts are adequate.
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White Mesa Mill -Standard Operating Procedures
SOP-PBL-RP-3
Book: Radiation Protection Manual, Section 3
Date: 1211 0 Revision: DUSA-4
Page 2 of 14
6. Repeat steps 4 and 5 until instrument response rapidly increases versus voltage level.
At this point, the detector is approaching potential differentials across the electrode
that may damage the detector.
7. Graph instrument response versus voltage applied.
8. Set equipment high voltage control to the optimum operating point. Record on graph
voltage selected.
9. Retain graph with calibration records.
3.1.2 Function Checks
Calibration function checks are required prior to use of radiation detection instruments
used at the Mill for the purpose of verifying that the instruments are operating at the same
efficiency as when they were calibrated by the calibration laboratory (i.e., within +1-10%).
Function checks are also used for verifying repeatability, reliability, and comparability of
an instrument's measurements from one period to another. By performing function
checks for extended time periods, or on a larger sample size, these goals are met.
Function checks involve two basic elements:
(1) calibration laboratory efficiency is compared to the instrument's efficiency on the
date of the function check; and
(2) the function check is verified with a check source having similar isotopic
composition as the one that was used by the calibration laboratory to calibrate the
instrument.
Function checks are made for all types of radiation survey instruments. The basic
principle in performing a function check is measuring the radiation field using a survey
instrument against a known amount of radiation from a calibrated source. These
measurements are made for the specific type of radiation occurring. For example, when
performing a beta/gamma survey, the instrument function check is performed using a
beta/gamma check source, such as a (SrY)-90. When performing an alpha survey, use an
alpha check source, such as Th-230 or Pu-239 for performing the function check.
Function checks are documented on the Calibration Check Forms (see Attachment A for
copies of forms to be used) for each specific instrument. They will be maintained in the
instrument's' calibration and maintenance file.
A number of radiation detection instruments are used at the Mill. An Instrument Users
Manual for each instrument is maintained in the calibration files, together with calibration
documentation. The Users Manuals are to be considered the primary reference for
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White Mesa Mill -Standard Operating Procedures
SOP-PBL-RP-3
Book: Radiation Protection Manual, Section 3
Date: 12/10 Revision: DUSA-4
Page 3 of 14
operating a particular instrument. This Standard Operating Procedure (SOP) is not
intended to replace the Users Manual, but rather to supplement the Manual by providing
steps to be performed for function checks. Before operating an instrument, personnel
should read the Users Manual and become familiar with the instrument's operation,
capabilities, and special features. Personnel will also receive on the job training on each
instrument.
3.1.3 Alpha Monitors
Alpha particles travel very short distances in the air due to their high ionization ability -
typically Y4 to ~ inch. Due to this limitation, alpha monitoring must be done at a distance
of Y4 inch or less between the detector face and the source. Alpha monitoring, to be
consistent, requires ensuring a consistent distance be utilized between the detector face
and the source. Alpha detectors read out in counts per minute (cpm). A correlation
relationship, known as the efficiency factor, between the meter response and the actual
disintegration rate of the source is used to determine actual calibration of the meter.
Radioactivity is measured in curies (Ci), which, by definition, is 3.7 x 1010 disintegrations
per second (dps), or 2.2 X 1012 disintegrations per minute (dpm). Another measurement
unit is the Becquerel, or one dps. Alpha radiation is usually monitored as dpm, per
surface area measured.
Radiation survey equipment used at the Mill for alpha surveys are listed in Appendices 1
and 2.
3.1.3.1 Calibration and Function Check Frequency
The frequency of calibration is specified in individual instrument user manuals and
manufacturer's specifications.
During production periods, the following frequencies are observed for calibration and
function checks of radiation detection instruments:
Calibration Function
~ Freguency Checks
1. Employee scans 6 month 5 days/week
2. Radon progeny 6 month each use
3. Respirator checks 6 month each use
4. Area fixed scans 6 month Daily or each use
5. Area wipe scans 6 month Daily or each use
During non-production periods, the following frequencies are observed:
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White Mesa Mill -Standard Operating Procedures
SOP-PBL-RP-3
Book: Radiation Protection Manual, Section 3
~
1. Employee scans
2. Radon progeny
3. Respirator checks
4. Area fixed scans
5. Area wipe scans
Calibration
Frequency
6 month
6 month
6 month
6 month
6 month
Date: 1211 0 Revision: DUSA-4
Function
Checks
bi-monthly
each use
each use
Daily or each use
Daily or each use
Page 4 of14
3.1.3.2 Function Check Procedures -Alpha Counters and Scaler Instruments
The following steps will be used for function checks for alpha counters and alpha scaler
instruments.
1. Tum the instrument on and place a calibrated alpha check source in the detector
holder on or the face of the detector.
2. Count the source for 1 minute and record this value in cpm.
3. Repeat step 2 four more times.
4. Average the five readings and divide the average in cpm by the known activity on the
alpha source. This is the efficiency of the instrument and detector.
5. Compare this efficiency with the efficiency obtained from the calibration lab. If the
efficiency comparison is within ± 10% deviation the instrument needs is calibrated if
not the instrument needs to be recalibrated.
6. If this efficiency comparison is within ±10% deviation the instrument is in calibration.
7. Proceed with monitoring activities.
3.1.3.4 Calibration Procedures
All radiation detection instruments used at the Mill are sent to a qualified offsite
laboratory every six months for calibration. However, if additional onsite calibration is
required the calibration procedures are:
1. Set the detector high voltage at the pnor determined operating point usmg an
electrostatic voltmeter.
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White Mesa Mill -Standard Operating Procedures
SOP-PBL-RP-3
Date: 12110 Revision: DUSA-4
Book: Radiation Protection Manual, Section 3 Page 5 of14
2. For counter/scalers (radon progeny/wipes), close the detector, without source present,
obtain a reading for a set time. This is a background reading.
3. Place a calibrated source for the type of radiation being measured in the source holder
and obtain reading.
4. Observe the counts per minute for both the background and the source.
5. Subtract the cpm value of background from the cpm value of the source to obtain the
net cpm.
6. Divide the net cpm value by the known dpm of the source. This is the percentage
efficiency of the instrument system for this energy source.
7. By dividing 100 by this efficiency, an efficiency factor is obtained.
8. Dpm equals the cpm divided by the efficiency of the instrument detector system:
Note: 1 curie = 2.22 E + 12 dpm
1 microcurie = 2.22 E + 6 dpm
1 picocurie = 2.22 dpm
3.1.4 Beta-gamma Monitors
Equipment utilized for beta-gamma monitoring is listed in Appendices 1 and 2.
3.1.4.1 Function Check Procedure
The following steps will be used for function checks on beta/gamma instruments:
1. Tum the instrument on and place the calibrated beta/gamma (SR-Y)-90 check source
on the face of the detector.
2. Let the reading stabilize to a constant value.
3. Record this value in cpm.
4. Divide this value by the known activity on the check source. This is the efficiency of
the instrument and detector.
5. Compare this efficiency to the efficiency obtained from the calibration laboratory. If
the efficiency comparison is within ± 1 0% deviation the instrument needs is calibrated
if not the instrument needs to be recalibrated.
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White Mesa Mill -Standard Operating Procedures
SOP-PBL-RP-3
Book: Radiation Protection Manual, Section 3
Date: 12110 Revision: DUSA-4
Page 6 of 14
6. If this efficiency comparison is within ±10% deviation the instrument is in calibration.
7. Proceed with monitoring activities.
3.1.4.2 Calibration
All beta-gamma survey instruments are sent out every six months for calibration.
Additional calibration, if necessary, may be perfonned on site using techniques described
in Reg. Guide 8.30, Appendix C -Beta Calibration of Survey Instruments for calibration
perfonned by a qualified calibration laboratory using the indicated source as listed in
Appendix 2.
3.1.5 Gamma Monitors
Instruments for gamma measurements are listed in Appendix 1.
3.1.5.1 Calibration
Independent calibration service laboratories perfonn calibration every six months.
Meters are calibrated to Cesium-I 3 7 or other radioisotopes as suggested by the calibration
laboratory or manufacturer. Most calibration service laboratories calibrate Beta/Gamma
instruments electronically in accordance with their standard calibration procedures.
However, electronic calibration basically consists of the steps described below:
1. Connect survey instrument to be calibrated to the model 500.
2. Tum both instruments on.
3. Record high voltage reading on model 500.
4. Set cpm and the range multiplier on the model 500 to the desired meter deflection.
The model 500 frequency controls consist of the three-digit readout, range selector,
coarse tuning knob, and the fine tuning knob. The three-digit readout is in cpm times
the frequency multiplier.
5. Calibrating survey instruments in cpm:
A. Set model 500 frequency to value that will provide a % meter deflection on the
survey instrument's highest count scale. Set pulse height/amplitude to twice
instrument input sensitivity.
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White Mesa Mill -Standard Operating Procedures
SOP-PBL-RP-3
Book: Radiation Protection Manual, Section 3
Date: 12/10 Revision: DUSA-4
Page 7 of 14
B. Adjust the range calibration potentiometer on the survey meter to provide correct
reading record.
C. De-code model 500 frequency to next lower value; then do the same for the
survey instrument.
D. Adjust the range calibration potentiometer for correct reading on survey
instrument. Record readings.
E. Repeat process until all ranges have been calibrated at % meter deflection. Record
readings.
F. Return to highest count scale on survey meter.
G. Set model 500 for Y4 scale deflection readings.
H. Survey instrument should read within ± 10% of model 500 frequency. Record
readings.
1) If readings are outside of the tolerance, re-calibrate for % meter deflection.
2) Tap instrument meter lightly to check for sticky meter. Meter tolerance is
± 3% from the initial readings to the final reading.
1. Decode M 500 to next lower scale. Check survey instruments for 1;4 scale reading.
Record.
6. Record input sensitivity.
A. Select the most sensitive amplitude range 0-5 mv on the model 500.
B. Observe meter on survey instrument.
C. Increase pulse amplitude, switching to next higher range, if necessary, until the
rate meter indicates a stable reading (i.e., further increase of pulse amplitude does
not cause an increase in meter reading). Now, decrease pulse height until the
survey instrument meter reading drops 15 ± 5%. Record this pulse height as the
instrument sensitivity.
D. If your instrument has a gain or threshold control to set instrument sensitivity, set
pulse height on the model 500 to desired sensitivity level. Now adjust your
instrument threshold or gain control until the rate meter reading is within 85 ± 5%
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White Mesa Mill-Standard Operating Procedures
SOP-PBL-RP-3
Book: Radiation Protection Manual, Section 3
Date: 12110 Revision: DUSA-4
Page 8 of 14
of its stable reading value (see step C). Record the pulse height as instrument
sensitivity.
7. Calibrating survey instrument to cps.
A. Set frequency in model 500. Divide model 500 readings by 60 to convert to counts
per second.
B. Repeat calibration steps as in item 5 above.
3.1.5.2 Frequency of Calibration
If electronic calibration is performed using the above method by the Radiation Safety
Department, the model 500 pulse generator will be sent out for calibration on an annual
basis.
3.2 PERSONNEL AIR SAMPLERS
The calibration procedure for personnel air samplers involves primary and secondary
calibration procedures. Samplers will be calibrated prior to each use by either of two
methodologies: bubble tube, electronic or mass flow determinations. Air samplers may
be calibrated to standard air conditions.
3.2.1 Bubble Tube Calibration Method
The Bubble Tube Calibration Method is a primary calibration method and does not
require corrections to or from standard conditions for temperature and pressure. Personal
air samplers are calibrated for the flow rate for the sampling being performed, typically 2-
4 liters per minute.
The equipment utilized is as follows:
1. Burette -1,000 ml capacity, 10 ml divisions
2. Support, iron, rectangular base, with rod
3. Burette clamps - 2
4. Soap solution, dish
5. Tubing, Gelman filter holder, filter media (0.8 micron glass fiber Gelman type AlE)
6. Stopwatch
7. Small screwdriver
8. Sample pump
The procedures utilized are:
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White Mesa Mill-Standard Operating Procedures
SOP-PBL-RP-3
Book: Radiation Protection Manual, Section 3
Date: 12/10 Revision: DUSA-4
Page 9 of14
1. Assemble a filter train -place a filter in an in-line filter. Attach two lengths of tubing
to each connector of the in-line filter holder.
2. Make sure the Burette is clean. Clamp the 1,000 ml Burette upside down on the ring
stand with the Burette clamps.
3. Attach the pump to be calibrated to one end of the filter train, connect the other end of
the filter train to the small end of the 1,000 ml Burette, as per Figure 1.
4. Check all tubing connections for air tightness.
5. Pour approximately Y:z inch (12 mm) of soap solution into the dish.
6. Start the pump.
7. Raise the dish up under the Burette opening, and then immediately lower the dish.
This should cause a film of soap to form over the Burette opening (i.e., a bubble).
Repeat this procedure until the film (bubble) will travel up the inverted Burette the
length of the graduation marks on the Burette without breaking.
8. When the film (bubble) has wetted the Burette inside and will travel the entire length
of the graduated area of the Burette, proceed with the actual calibration run.
9. Quickly form three bubbles and start the stopwatch when the middle bubble is at the
bottom graduation line (actually the 1,000 ml mark, but for purposes here, it will be
called the "zero" line).
10. Time the travel of the bubble from the zero line to the top line of the graduated
distance (0 ml). Since the capacity of the Burette is 1,000 ml (1.0 liter), then the
volume of air that is displaced above the bubble (i.e., needed to raise the bubble) is
1.0 liter. Stopping the stopwatch at the top mark is the time elapsed for the pump to
accomplish this. The rate of rise of the bubble through the apparatus is the flow rate
of air being pulled by the pump.
11. Increase or decrease the pump collection rate by adjusting the appropriate screw or
knob designed for this purpose.
12. Set the pump flow collection rate to the desired valued usually between 2 and 4 liters
per minute for low volume collection pumps and between 30 and 80 liters per minute
for high volume collection pumps.
3.2.2 Mass Flow Method
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White Mesa Mill -Standard Operating Procedures
SOP-PBL-RP-3
Date: 12110 Revision: DUSA-4
Book: Radiation Protection Manual, Section 3 Page 10 of 14
Mass flow meters are manufactured equipment designed to measure air collection flow
rates for a variety of purposes. Mass flow meters may be subject to temperature and
pressure corrections of air movement depending on whether they are
calibrated/manufactured for standard conditions.
Utilizing an air mass flow meter, traceable to NBS, the airflow rate of pumps can be
quickly adjusted to correct standard flow rate conditions. However, the mass flow meter
must be calibrated annually using a primary calibration method.
The equipment consists ofthe following:
1. Kurz air mass flow model 543 or equivalent
2. Suitable filter head adapter connections
3. Filter heads with filter media
4. Pump to be calibrated
Note: The meter is calibrated directly in standard air conditions -25° c., 29.82" Hg.
The procedures utilized are:
1. Ensure pump batteries are fully charged.
2. Ensure flow meter batteries are fully charged.
3. Assemble filter train.
4. Connect (with a suitable adapter) the Kurz probe onto the filter train. Ensure an
airtight seal with tape, if necessary.
5. Set the meter function switch to the highest range: 40 std liters per minute.
6. Tum the pump on.
7. Select appropriate range on the meter. (Do not allow meter needle to be forcibly
pegged.)
8. Adjust the pump flow rate as necessary to desired flow rate. Allow the meter to
stabilize before adjustment of the pump.
9. Meter reads directly in standard air conditions, correcting for temperature and
barometric pressure.
Pump is now calibrated. Low volume pumps are set at 2 to 4 lpm.
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White Mesa Mill -Standard Operating Procedures
SOP-PBL-RP-3
Date: 12110 Revision: DUSA-4
Book: Radiation Protection Manual, Section 3 Page 11 of 14
3.2.3 Electronic Calibration Method
The electronic primary gas flow calibration is the primary calibration method and does
not require corrections to or from standards conditions for temperature and pressure.
Personal air samplers are calibrated for the flow rate for the sampling being performed
typically 2 - 4 liters per minute. Area Airborne high volume air samplers should be
calibrated to a minimum of 40 liters per minute.
The equipment utilized is as follows:
1. UltraFlo Primary Gas Flow Calibrator, or equivalent
2. Soap solution
3. Tubing
4. Small screwdriver
5. Sample pump
The procedure proceeds as follows:
1. Remove the two nipples on the back ofthe UltraFlo Primary Gas Flow Calibrator.
2. Attach the connection tubing from the top nipple to the sample pump.
3. Tum calibrator on.
4. Tum sample pump on.
5. Press the plunger style button on top of the soap dispensing portion of the device.
6. Write down the digital reading from the calibrator device.
7. Repeat steps 5 and 6 three times.
8. Take an average of the three readings.
9. If the sample pump requires adjustment, take the screwdriver and adjust the set
screw on the face of the sample pump and then repeat steps 5 through 7.
10. After the sample pump is calibrated, document the calibration on the Breathing
Zone/Radon or the High Volume Calibration Sheet depending on which device is
being calibrated, in the Radiation department.
11. Replace nipple caps on the back of the calibrator.
3.3 AREA AIR SAMPLERS
The calibration procedure for area air samplers involves one of the following procedures;
Kurz Mass Flow, Wet Test Gas Meter, Electronic or Bubble Tube Method.
3.3.1 Kurz Mass Flow Method
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White Mesa Mill -Standard Operating Procedures
SOP-PBL-RP-3
Book: Radiation Protection Manual, Section 3
Date: 12/10 Revision: DUSA-4
Page 12 of 14
Repeat procedures discussed in 3.2.2 -except -airflow rate is adjusted to 40 slpm and
samplers utilized are:
1. Eberline RAS-l
2. Scientific Industries Model H25004
3. Equivalent
3.3.2 Wet Test Gas Meter Method
The wet test gas meter method utilizes a Precision Scientific wet test meter rated at one
cubic foot per revolution of the main dial. This method is used to calibrate the Kurz air
mass flow meter in addition to direct calibration of the area air samplers.
The procedures are:
1. Attached coupling to sampler filter assembly; secure it with tape.
2. Connect wet test meter hose to coupling.
3. Check water level of wet test meter. The needle should be on slightly above the water
level.
4. Check the thermometer temperature of the wet test meter. Record this on the
calibration sheet. Assume that the wet and dry bulb temperatures are the same.
5. Tum on the sampler. Check the west test meter's manometer reading. This reading is
obtained by adding the left and right column values. (A typical reading might be .3).
Log these values for each ball height on the "Static pressure ... H20" column.
6. For the following sampler approximate settings, pull one cubic foot of air through the
wet test meter and record the time (in seconds) for each: 20, 30,40, and 50 lpm.
Sampler Calibration Procedures -Calculations and Equations
1. To convert the static pressure (of the manometer attached to the wet test meter) from
inches of water to inches of mercury, divide the number of inches to water by 13.6.
Example: 0.4/13.6-0.02941176" Hg
2. To compute the actual flow rate ("Q rate act. lpm"), first divide the number of cubic
feet by the number of seconds. Example: 1 ft.3/90 sec = .01111 ft?/awx. Convert
the cubic feet to liters. The conversion factor is 28.317. Example: .01111 ft? /sec x
28.317 L ft.3 = .3146 Llsec. Multiply this by 60 to convert from seconds to minutes.
Example: .3146 Llsec x 60 sec = 1888 Lim or 18.88 lpm.
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White Mesa Mill -Standard Operating Procedures
SOP-PBL-RP-3
Book: Radiation Protection Manual, Section 3
Date: 12/10 Revision: DUSA-4
Page 13 of 14
3. Using the "Vapor Pressures of Water" chart, find the vapor pressure inside the wet
test meter by matching the wet bulb temperature with the corresponding vapor
pressure. This number is the vapor pressure at the standard wet bulb (Pvpstw).
4. Find the vapor pressure at dewpoint using this formula: Pv dewpoint = Pvpstw =
0.0003613 (td-tw) Bp (Where +d = dry bulb temp; tw = wet bulb temp; bp =
barometric pressure in inches of mercury.) Assume that the dry bulb temperature
and the wet bulb temperature are the same, so the difference between them will
always be zero. Thus, Pv dewpoint will equal Pvpstw.
5. Determine the actual air density (D act) with this formula:
D act = 1.327
td + 459.67 [(Pg-Sp) -0.378 (Pv dewpoint)]
(Where td -dry bulb temp in degrees F.; Bp = barometric pressure in inches of
mercury; Sp = static pressure of wet test meter in inches of mercury.)
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White Mesa Mill-Standard Operating Procedures
SOP-PBL-RP-3
Date: 1211 0 Revision: DUSA-4
Book: Radiation Protection Manual, Section 3
Example:
D act = 1.327
70.5 + 459.67
= 1.327
530.17
[(24,8031 -0.02941176) -0.378 (.875)]
(24,773688 -0.33075)
= (0.00250297) (24.442938)
D act = 0.06117996
Log this in "Air Density Ibs/ft3" column of log sheet.
Page 14 ofl4
6. Find the flow rate ofthe sampler at standard conditions (Q std) using this formula:
Q std = Q act D act
D std
(Where D std = .075 lbs/ft3)
(i.e., Q std = 18.88 (0.06117996)
0.075
18.88 (0.8157328)
= 15.40
Q std = 15.40 (write this down for each position in the Q 0.075 column)
3.3.3 Bubble Tube Method
Refer to Section 3.2.1 to perform this method.
3.3.4 Electronic Calibration
Refer to Section 3.2.3 to perform this method.
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