rALLIBURTON SERVICES

GOVERNMENT REGULATIONS DEPARTMENT

RON BECHTELManager

DAN KELLYRegulatory Specialist

Writer's Direct Dial Number

(405)251-3749

Division of Fuel Cycleand Material Safety

Office of Nuclear MaterialSafety and Safeguards

U. S. Nuclear Regulatory CommissionWashington, D. C. 20555

DRAWER 1431, DUNCAN, OKLAHOMA 73536Senior Environmental Engineers

STEVE BURFORDRALPH HOUSERBILL JONES

Environmental EngineerJOHN PRESGROVE

Radiation Safety OfficersRICHARD LEONARDISTEVE HOOK

February 14, 1984

-n,

-7v

Dear Sirs:

Enclosed is a completed application for renewal ofHalliburton Services Byproduct Material License Number35-00502-03 which has an expiration date of February 29, 1984.

Also enclosed is a check for the amount of $460.00 madepayable to the U. S. Nuclear Regulatory Commission which isthe fee for category 3.A.

Sincerely,

Dan G. Kelly

DGK/cddAttachments

' .... ....!n / Informatd

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BB0is - 5 73011~8olc4 l O72\fP ~41., 6OqO

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NRC Form 313 I U.S. NUCLEAR REGULATORY COMMISSION 1. APPLICATION FOR:012-81) (Check and/or complete as appropriate)10 CFR 30

APPLICATION FOR BYPRODUCT MATERIAL LICENSE

INDUSTRIAL a. NEW LICENSE

See attached instructions for details. b. AMENDMENT TO:LICENSE NUMBER

Completed applications are filed in duplicate with the Division of Fuel Cycle and Material Safety,Office of Nuclear Material Safety, and Safeguards, U.S. Nuclear Regulatory Commission, c RENEWAL OF:Washington, DC 20555 or applications may be filed in person at the Commission's office at LICENSE NUMBER1717 H Street, NW, Washington, D. C. or 7915 Eastern Avenue, Silver Spring, Maryland. X 35I00502U0

_____________________________________ _______________ 3 5-00502-032. APPLICANT'S NAME (Institution, firm, person, etc.) 3. NAME AND TITLE OF PERSON TO BE CONTACTED

Hallibur ton Services REGARDING THIS APPLICATIONDan G. Kelly

TELEPHONE NUMBER: AREA CODE - NUMBER EXTENSION TELEPHONE NUMBER: AREA CODE - NUMBER EXTENSION

405/251-3760 405/251-37494. APPLICANT'S MAILING ADDRESS (Include ZiJ Code) 5. STREET ADDRESS WHERE LICENSED MATERIAL WILL BE USED

(Address to which NRC correspondence, notices, bulletins, etc., - (Include Zip Code)shouldbesent.) Halliburton Services, North 40, Osage RoadP. 0. Drawer 1431 1 Research Center, 1500 South Second St.Duncan, Oklahoma 73536 v RAYFRAC Bldg., 1409 South 13th Street

Duncan, Oklahoma 73536

(IF MORE SPACE IS NEEDED FOR ANY ITEM, USE ADDITIONAL PROPERLY KEYED PAGES.)6. INDIVIDUAL(S) WHO WILL USE OR DIRECTLY SUPERVISE THE USE OF LICENSED MATERIAL

(See Items 16 and 17 for required training end experience of each individual named belowl

FULL NAME TITLE

a. Dan G. Kelly Radiation Safety Officer

b. Richard A. Leonardi, Jr. Radiation Safety Officer

.. Stephen E. Hook Radiation Safety Officer

7. RADIATION PROTECTION OFFICER Attach a resume of person's training and experience as outlined in Items16 and 17 and describe his responsibilities under Item 15,

Same as 6. a., b., and c. Resume's attached

8. LICENSED MATERIAL

L ELEMENT CHEMICAL NAME OF MANUFACTURER MAXIMUM NUMBER OF

I AND AND/OR AND MILLICURIES AND/OR SEALED

N MASS NUMBER PHYSICAL FORM MODEL NUMBER SOURCES AND MAXIMUM ACTI-E (If Sealed Source) VITY PER SOURCE WHICH WILLBE POSSESSED AT ANY ONE TIME

NO. A B C D

(1)

(2) See Attachment #1

(3) See Attachment #i

(4)S.....DESCRIBE USE OF LICENSED MATERIAL

E

(1) See Attachment #1

8804250077 860306(2) REG4 LIC30

35-00502-03 PDR13)

(4)

NRC FORM 313 (12-81)

16985

9. STORAGE OF SEALED SOURCESL CONTAINER AND/OR DEVICE IN WHICH EACH SEALED NAME OF MANUFACTURER MODEL NUMBERN SOURCE WILL BE STORED OR USED.E

NO. A. B. C.

(I) See Attachment #2 Halliburton Services 10SD

(2) These are draw-ings for the newer 8" 20SD

( densometer, Model 10OSD, other drawings 55SDare presently on file at NRC. 55SD

(4) 100SD

10. RADIATION DETECTION INSTRUMENTS

TYPE MANUFACTURER'S MODEL NUMBER RADIATION SENSITIVITYL OF NAME NUMBER ' AVAILABLE DETECTED RANGEN INSTRUMENT (alpha, beta, (milliroentgens/hour

NO. gamma. neutron) or counts/minute)A B C D E F

Multi-channel(1) Analyzer Canberra one all

(2) Survey Meter Victoreen Thyac III one beta-gamma

(3) Survey Meter Ludlum 2 five beta-gamma (b)(4).(b)(7)(F)

14) Survey Meter Ludlum 15 one neutron

11. CALIBRATION OF INSTRUMENTS LISTED IN ITEM 1010 a. CALIBRATED BY SERVICE COMPANY 0b. CALIBRATED BY APPLICANT

NAME, ADDRESS, AND FREQUENCY Attach a separate sheet describing method, frequency and standardsused for calibrating instruments,

Ludlum Measurements, Inc. Six Month

501 Oak St. FrequencySweetwater, TX 79556

12. PERSONNEL MONITORING DEVICESTYPE SUPPLIER EXCHANGE FREQUENCY

(Check and/or complete as appropriate.) (Service Company) CA BC

051) F ILM BADGE 0MONTHLYNuclear Sources & Services, Inc.

9J (2) THERMOLUMINESCENCE Dosimeter Corporation ID QUARTERLYDOSIMETER (TLD) Victoreen Corporation

(2(3) OTHER (Specify): Direct Reading El OTHER (Specify):

dosimeters for occasional DRD are calibratedand drift rested

users only (See Attachment #4 annually

13. FACILITIES AND EQUIPMENT (Check were appropriate and attach annotated sketch'es) and description(s).

9] a. LABORATORY FACILITIES, PLANT FACILITIES, FUME HOODS (include filtration, if any), ETC.

E? b. STORAGE FACILITIES, CONTAINERS, SPECIAL SHIELDING (fixed and/or temporary), ETC.01 c. REMOTE HANDLING TOOLS OR EQUIPMENT, ETC. See Attachment V5

0 d. RESPIRATORY PROTECTIVE EQUIPMENT, ETC.

14. WASTE DISPOSALa. NAME OF COMMERCIAL WASTE DISPOSAL SERVICE EMPLOYED Our waste is returned to Gulf Nuclear, Inc

to their licensed holding facility in Odessa, Texas.

b. IF COMMERCIAL WASTE DISPOSAL SERVICE IS NOT EMPLOYED, SUBMIT A DETAILED DESCRIPTION OF METHODS WHICH WILLBE USED FOR DISPOSING OF RADIOACTIVE WASTES AND ESTIMATES OF THE TYPE AND AMOUNT OF ACTIVITY INVOLVED. IFTHE APPLICATION IS FOR SEALED SOURCES AND DEVICES AND THEY WILL BE RETURNED TO THE MANUFACTURER, SO STATE

N/A

NRC FORM 3131112-81)

INFORMATION REQUIRED FOR ITEMS 15, 16 AND 17

Describe in detail the information required for Items 15, 16 and 17. Begin each item on aseparate page and key to the application as follows:

See Revised "Radiation Safety Manual" attached.

15. RADIATION PROTECTION PROGRAM. Describe the radiation protection program as appropriate forthe material to be used including the duties and responsibilities of the Radiation Protection Officer,control measures, bioassay procedures (if needed), day-today general safety instruction to be followed,etc. If the application is for sealed source's also submit leak testing procedures, or if leak testing will beperformed using a leak test kit, specify manufacturer and model number of the leak test kit.

16. FORMAL TRAINING IN RADIATION SAFETY. Attach a resume for each individual named inItems 6 and 7. Describe individual's formal training in the following areas where applicable. Includethe name of person or institution providing the training, duration of training, when training wasreceived, etc.

See Attached Resume's

a. Principles and practices of radiation protection.

b. Radioactivity measurement standardization and monitoringtechniques and instruments.

c. Mathematics and calculations basic to the use and measurement ofradioactivity.

d. Biological effects of radiation.

17. EXPERIENCE. Attach a resume for each individual named in Items 6 and 7. Describe individual'swork experience with radiation, including where experience was obtained. Work experience or on-the-job training should be commensurate with the proposed use. Include list of radioisotopes andmaximum activity of each used.

See Attached Resume's

18. CERTIFICATE(This item must be completed by applicunt)

The applicant and any official executing this certificate on behaff of the applicant named in Item 2,

certify that this application is prepared in conformity with Title 10, Code of Federal Regulations,

Part 30, and that all information contained herein, including any supplements attached hereto, is true

and correct to the best of our knowledge and belief,

WARNING.-18 US.C., Section 1001; Act of June 25, 1948; 52 Stat. 749; makes It a criminal offense to make a willfully false statement orrptesaftation to any deprtment or agency of the United States as to any matter wr.hin its jurisdiction,

a. LICENSE FEE REQUIRED b. CERTIF ING OFFICIAL (Sntu(See Section 170.31. 10 CFR 170) Z -

c. NAME (Type or print)Dan G. Kelly

d. TITLE(1) LICENSE FEE CATEGORY: 3.A. Radiation Safety Officer

e. DATE1 .2) CENSE FEE ENCLOSED: s 46(.00 ý /9 0/

NRC FORM 313 1 (12.81) -PO 611"26

ATTACHMENT #1

Item 8, A, B, C, D and E.

(1) Scandium-46

Ll (2) Iridium-192

(3) Zinc-65

(4) Iron-59

V (5) Silver-110m

L- (6) Lanthinum-140

L'(7) Cobalt-60

I/(8) Any nuclide withAtomic Numbers33 through 83

(9) Cesium-137

(10) Hydrogen 3

v (11) Nickel-63

(12) Americium, 2412c

Any

Any

Any

Any

Any

Any

Any

ContaminatedReacter-Components

Sealed Sources U. S. Nuclear 375General Nuclear CS-1000Gamma Industries CS-1000Gammatron GT-GHPGulf Nuclear CS-2New England Nuclear NER-572Texas Nuclear 570-57157CMonsanto )Amersham CDICQ4935) R/A-D3M Company )Kay-Ray - Any Model

Campbell Pacific NuclearModel CPN 131

Sealed LightSources

PlatedSources

Hewlett-Packard ModelNo. 19303

Detector Cells

Sealed Sources Monsanto ResearchX-602-04-101 through 106CammatronAN-HPAmersham-Am NQ 5478

(13) Ra-226 Sealed Sources Gammatron, Inc.GT-CK

ATTACHMENT #i

E

(1) through (7)

(3) and (4)

(8)

(9)

(10)

(11)

(12)

(13)

(12) and (13)

To be used for tracer sand manufacture and liquid isotope supply

for field operations.

Also used for the manufacture of downhole markers, such as cementplug or collar workers.

Laboratory testing of decontamination procedures.

To be used for research, development and manufacture of densometerand density gauging devices.

For research and development as defined in CFR 10, 30, 30.4(q).

For use in gas chromatographs for sample analysis.

To be used for research, development and assembly of downholelogging instruments,

To be used as gamma calibrator for density gauging sources.

Sources are transferred or exported to our International WelexOperations.

-2-

ATTACHMENT #3

Survey Meter Calibration Procedures

Survey meters will be calibrated with a 163 mCiCesium-137 source model TECH/OPS 77302 contained in a Techni-cal Operations model 773 instrument calibration device. (Abrochure is enclosed for your information).

The device will be used at various locations. OnlyHalliburton or its subsidiaries survey meters will be cali-brated. This will not be a customer service. Thecalibration device is a DOT 7A container and will be securedin the vehicle during transportation to prevent shiftingand/or damage to the device. Set up at each location will bein such a fashion that no individual will be permitted toenter the restricted area. The calibration will be used inan area in which the wall is at least sixteen (16) feet fromthe source. This will insure that the 2 mR/hr area will beunder visual surveillance at all times.

The output of the 163 mCi Cesium-137 source is 52.2mR/hr at 1 meter. The inverse square law will be used todetermine the various calibration points to be used in theradiation field. The attenuators provided on the device willalso be utilized for point location. Each instrument will becalibrated at two points on each scale. The two points willoccur at approximately 30% and 70% of full scale, except whenthe full scale reading is equal to or less than 0.5 mR/hrthat scale will be calibrated at just one point, nearmid-range. If the instrument cannot be adjusted to readwithin ±20% of any correct value, it will be repaired.

Operational Procedures

1. Desired points in the radiation field will bedetermined by using any needed decay factor and theinverse square law and attenuators provided on thecalibration device.

2. When the desired points are determined thecalibrator will be set up for use.

3. The detector will be placed in the desiredlocation. It will be insured at this time that theentire detector is located so the sensitive volumeis covered by the radiation field.

4. The source will be exposed and the instrument willbe read. If the desired reading is obtained thenext point on that scale will be tested in the samemanner. If the desired reading is not obtained,

-2-

the source will be retracted to the shieldedposition. Then adjustments to the meter will bemade. The source will then be exposed again todetermine if the reading is now acceptable. Thismethod will continue until the desired reading isobtained or it is determined that the instrumentmust be repaired before use. Each scale will bechecked in the same manner.

A copy of the calibration certificate and metersticker is enclosed for review.

M ALLIBURTON SERVICESDRAWER 143?. DUNCAN, OKLAHOMA 73533

DEPARTMENT OF GOVERNMENT REGULATIONS

RON BECHTEL

Manager Certificate of CalibrationWriTer's Direct Dial Number

District

Mfg Model Ser. No.

Mfg Detector Model Ser. No.

Calibration Date Cal. Due

Calibration Interval: 6 months Texas License 7-1835.

Instrument: In Tolerance Out of Tolerance Needed Repair

Instrument Range

0 0 - 50 m R/hr.0 0 - 2.0 r/hr,

Range Indicator

Instrument Calibrator

Tech/Ops Model 773CS-137 @ 163;0 mCi @Source S/N S-433Output 0.0522 r/hr.

Measured or (mR/hr)Calculated Field

on 6-29-83

@ 1 meter

InstrumentReading (mR/hry

Halliburton Services certifies that the above instrumentcalibrated by a standard source traceable to NBC.

Calibrated by

0 A Halliburton Company

has been

CALIBRATION DATE:

CALIBRATED BY:

IN ACCORDANCE WITH

TEXAS LICENSE # 7-1835

F--

Tech/Ops Model 773Instrument

Calibration DeviceOperation Manual

#'~

TECHNICAL OPERATIONS, INC.Radiation Products Division

Burlington, Mass. 01803Phone (800) 225-1383 (toll free)[in Mass. call (617) 272-2000]

Technical Data

Size:

Weight:

Source:

TransportStatus:ShieldingMaterial:

5 in (12.7 cm) wide, 5 in (12.7cm) deep, 8.5 in (21.6 cm) high(with attenuators) 52 lbs. (24kg)(without attenuators) 45 lbs.(20 kg)Model -77302, " 7Cesium, 150millicuriesDOT Specification 7A TypeA PackageLead Approx. 29 lbs. (13 kg)

General

The Model 773 is a small, portable radiationsurvey instrument calibration device. The unitconsists of a 150 millicurie "'Cesium sourcepermanently attached t19 a movable source rodwhich is installed in a 1bad shield casting. Thesource is exposed by raising the source rodwhich positions the source in a 360 x 200 col-limated beam port.The unit is equipped with three attenuators(Transmission of 0.25, 0:10 and 0.10) to allow asurvey instrument with. three ranges to becalibrated at 20% and 80% of each rangewithout changing the position of the survey in-strument. The Model '773 can be used tocalibrate survey instruments with ranges up to2000 milliroentgens per hour.The unit is equipped with a carrying handlewhich also serves as a sourceolocking bar toprevent unauthorized use of the calibrator. Ashipping cover is also attached to provide andadditional means of securing the source.

Receiving

Survey the device for excessive radiation levels.The device should have radiation levels lessthan 200 mR/hr at the surface and less than 10mR/hr at three feet from the surface. Inspectthe device for shipping damage and insure thatthe device is locked.

Safety Precautions

The Model 773 Meter Calibration Device con-tains a 150 millicurie "'Cesium source that

emits gamma radiation which can cause injuryif improperly used. Disassembly of the device orremoval of the source requires special equip-ment. We recommend that any service requiringdisassembly of the device or removal of thesource be performed by the manufacturer.

Instrument Devices

Although the device has radiation levels whichare well below the maximum radiation level per-mitted on storage containers, personnel shouldnot stay close to the device any longer thannecessary.Precautions should be taken to store the instru-ment calibration device in an area that meetsthe requirements of Title 10 Code of FederalRegulations 20.202(b) (2), 20.203(b) and20.203(e).It is recommended that personnel operating theequipment use a calibrated and operable surveyinstrument and wear appropriate personnelmonitoring devices. The radiation level at thesource rod when the source is in the "operate"position is approximately 50 milliroentgens perhour.Movement of the source rod should be ac-complished as expeditiously as practicable. Analternative method of raising the source rodwould be the use of a string and pulley arrange-ment.In no case should anyone enter the area of theradiation beam or expose any part of his bodyto the radiation beam.

Preparation for Use

Place the source shield in a restricted area sothat the directional port is aimed horizontally.

-*To minimize the effects of scattered radiation,,'1the uniLshould_ be 16 feet from any wall in the,idirection of the primary-beam.

Position a support horizontally from the Model773 Instrument Calibration Device as shown inFigures 1 and 2.Restrict access to the area where the radiationlevel is in excess of 2 milliroentgens per hour.(See Figure 4).

Operation

Note: To properly calibrate a survey instrumentit is necessary to check the instrumentsresponse at two points on each of the in-struments ranges. These points must beseparated by at least 50% of the full scalereading. The instruments reading should agreewith the actual radiation intensity within 10%to be in proper calibration.The following procedure is designed for asurvey instrument with three scales and a rangeof 0-1000 mr/hr. For instruments with differentranges, the procedure will be similar but thepoints will differ.

1. Turn on the survey meter and allow it to"warm up" for approximately 10 minutes.

2. Determine the activity of the source onthe date of calibration from the decaychart provided with the source.

3. Determine the distance from the sourceat which the radiation intensity would be800 mr/hr (use Figure 3).

4. Using the tape measure attached to theModel 773, place the survey meter suchthat the axis of the detector is located atthe proper distance from the source asdetermined above.

Note:

The survey meter should be located so thatthe center of the detector is at the correctdistance and centered on the center line ofthe radiation beam. The axis of the detectorshould be perpendicular to the centerline ofthe radiation beam. Depending upon thephysical size of your survey instrument, itmay be necessary to mount it somewhathigher than the bench surface. When the pro-per geometry for your instrument has beenestablished, use the same physical arrange-ment consistently in future calibration opera-tions.At short distances, using survey instrumentswith large detector volumes, the radiation in-tensity will not be uniform across the detec-tor. Consideration should be given to this ef-fect when determining the radiation inten-sities to be checked,

5. Unlock the handle of the Model 773. Re-

move the shipping plate. Remove all theattenuators from the radiation beam.

6. Standing away from the radiation beam,expose 'the source by manually raisingthe source rod. Note and record thesurvey meter reading, return the sourceto the stored position. The actual intensi-ty is 800 mr/hr. If the reading is within ±10% of the actual intensity, continuechecking the instrument. If the instru-ment reading is not within ± 10% of theactual intensity, the instrument must beadjusted and recalibrated.CAUTION: Do not enter the area of theradiation beam while the source is expos-ed.

7. Place the 0.25 attenuator in the beam.Repeat step 6; the actual intensity is 200mr/hr.

8. Remove the 0.25 "attenuator from theand place a 0.10 attenuator in the beam.Repeat step 6; the tactual intensity is 80mr/hr.

9. Place the 0.25 attenuator in the beam.Repeat step 6; the actual intensity .is 20mr/hr.

10. Remove the 0.25 attenuator from thebeam and place the other 0.10 attenuatorin the beam. Repeat step 6; the actual in-tensity is 8 mr/hr. _

11. Place the 0.25 attenuator in the beam.Repeat step 6; the actual intensity is 2mr/hr.

Leak Testing

The Tech/Ops Model 773 Meter Calibration Kitcontains a "'Cesium source which must be leaktested at intervals not to exceed six months.This may be accomplished using the Tech/OpsModel 518 leak test kit.

1. Place the Model 773 calibrator In a re-stricted area.

2. Remove the lock and rotate the handlefrom the top of the source rod. Removethe shipping cover.

3. Moisten the leak test swab with EDTAsolution. Blot off the excess.

4. Wipe around the top of the source rod.5. Standing away from the beam port, raise

the source rod to the open position and

wipe the exposed source rod thoroughly.6. Place the leak test swab in the'plastic

envelope.7. Set the survey meter on its most sensitive

range and place the meter in a lowbackground area. Move the swab, in itsplastic envelope, to the meter, not themeter to the swab.

8. If the meter indication is less than 0.2mr/hr above background, place theplastic envelope with the swab into themailing box and mail to Technical Opera-tions, Inc., Burlington, Massachusetts.BE SURE TO FILL OUT AND RETURN

THE IDENTIFICATION SHEET.9. If the swab should show more than 0.2

mr/hr. DO NOT MAIL. Contact TechnicalOperations, Inc. for specific instructions.

Note:

The wipe test swab will be subjected to aprecise radioassay when received byTech/Ops and a leak test certificate will bemailed promptly. This certificate must bekept with your records as it is subject toN.R.C. inspection.

169985

BEAM 360Model 773_

t

FIGURE 1

I~i[H11cBEAM 200

Model 773

FIGURE 2

Figure 3

0)

0

C

0

0

V

10

8

6

4

3

150 100 80 60 40 20

Activity (mCi)

Distance to 800mR/hr isodose line as a Function of Activity

Figure 4 "

.4-

0)

U

C

04-

U)

V

150 100 80 60 40 20

Activity (mCi)

Distance to 2mR/hr isodose line as a Function of Activity

-"'nALLI BURTON SERVICESDRAWER 1431, DUNCAN, OKLAHOMA 73536

GOVERNMENT REGULATIONS DEPARTMENT Senior Environmental Engineers

RON BECHTEL STEVE BURFORD

Manager RALPH HOUSERBILL JONESDAN KELLY

Regulatory Specialist Environmental EngineerJOHN PRESGROVE

Writer's Direcr Dial Number Radiation Salety Officers

RICHARD LEONARDISTEVE HOOK

Halliburton Services wishes to submit the following proposal regardingthe use of self-reading pocket dosimeters as a primary personnelmonitoring device for those employees that are only occasionallyexposed to sources of radiation for short periods of time.

Halliburton is currently utilizing TLD personnel monitoring providedby NSSI durinq routine use of radioactive -tracers. Any employee whoroutinely handles radioactive material is provided-and required to wear ETLD device. However, on occasion, a situation may arise involvingthe transport, or the limited handling of radioactive material at alocation where all TLD monitored employees are either on a currentjob location or obligated for a number of reasons. This infrequentsituation creates an unnecessary burden on the local Halliburton fieldcamp during their routine field operations. This situation may involvecostly job delays and/or individuals that must travel several milesin order to provide a TLD monitored employee to merely transportradioactive material to a job location or to another Halliburtonfield camp.

Halliburton requests the Agency's consideration on the followingproposal for the use of self-reading pocket dosimeters in lieu of theTLD for personnel who would on occasion transport and/or handleradioactive tracer. The above mentioned occasional user would beinstructed in Halliburton's Operating and Emergency Procedures and betrained in the use of radiation survey equipment and have in hispossession the following:

1. "Emergency Procedures" in case of an accident and including anEmer9gncy Telephone Number Call List.

M. NA HýOowtm, ("n-, -,,

2. Completed "Halliburton Shipping Manifest".

3. Appropriate radioactive material receipt, transfer, ordisposal record.

4. Current "Vehicle Survey".

5. Recently calibrated survey meter.

The use of self-reading pocket dosimeters under the above conditionswould necessitate a quality assurance program to insure the accuracyand operational integrity of each pocket dosimter. Halliburtonproposes that each pocket dosimeter in use to be calibrated on asix month interval with a leak rate and calibration/response testbeing performed with a record of calibration being on file forinspection by the Agency.

Please find the following enclosed documents:

1. Pocket dosimeter User Procedure "Self-Reading Dosimeter Use".

2. "Pocket Dosimeter/Accuracy and Leak Test" procedure.

3. Halliburton's in-house "Daily Dosimeter Reading" report.

4. Copy of TRCR 21-3 form for transcription of quarterlyexposure from above item #3.

5. Copy of Halliburton's in-house pocket dosimeter calibrationcerti ficate.

Halliburton submits the above procedure for your consideration. Letme reemphasize the intent of Halliburton to use the self-readingpocket dosimeter as a primary personnel monitoring device only on alimited basis and during occasional situations involving limitedtransport/handling of radioactive material. Halliburton will continueto utilize the TLD monitoring device for all employees routinelyhandling radioactive material.

Please feel free to contact me regarding any questions you might have.

Sincerely yours,

Richard A. LeonardiRadiation Safety Officer

EnclosuresRAL/sjh

/I

SELF-READING DOSIMETER USE

PURPOSE:

This procedure describes the wearing, handling, and reading ofself-reading pocket dosimeters.

PRINCIPLES:

The self-reading dosimeter provides a quick, reasonably accurateand simple method of keeping accumulated radiation dose of indivi-duals working in various levels of radiation fields. The field willdetermine what range of dosimeter must be worn, generally fallinginto three categories: O-200MR, O-500IR, O-I00MR, or combinationof these three. The dosimeter reading is noted before entry intothe radiation area, and upon exit. The difference is the amountof radiation dose the individual received during that work.

EQUIPMENT NEEDED:

o Victoreen and /or Dosimeter Corporation of America (DCA)self-reading dosimeters of approriate range with validcalibration sticker.

o DCA Charger/Reader.

o "Daily Dosimeter Reading" form.

PRECAUTIONS:

o Insure proper range dosimeter with valid calibration stickerin use.

o Wear dosimeter on upper trunk of body and cluster dosimeterswhen used in conjunction with other dosimeters, film badges,or TLD badges.

o Handle carefully to avoid dropping, which may result inerroneous reading.

o Exercise care in handling dosimeter to avoid contaminationfrom gloves.

,-.\ Page 2SE ,EADING DOSIMETER USE

PRECAUTIONS continued...

o Immediately report any lost, or off scale dosimeters to

appropriate personnel.

USER INSTRUCTIONS:

1. Obtain properly calibrated and appropriate range dosimeteras instructed.

2. Zero dosimeter using charger/reader, or align hairlineon scale at lower end of scale.

3. Follow charging instructions as posted on dosimetercharger/reader.

4. Read to the nearest half of the small division.

5. Record the initial dosimeter reading on the "Daily DosimeterReading" form.

6. Check and read the dosimeter often while in the radiationarea. When in a Beta radiation field, the dosimeter shouldbe clipped and taped on the outside of your clothing orAnti-C clothing for correct recording of exposure and easeof reading. If the dosimeter is off-scale, immediatelyleave the controlled area and report to appropriate personnel.

7. Report any defective dosimeters to approproate personnel.

8. For any dosimeters which go off-scale, the assigned dosereceived by an individual shall be determined by theRadiation Safety Officer after consultation with theexposed individual and any knowledgeable person involved.

POCKET DOSIMETER ACCURACY/LEAK TEST

PURPOSE:

This procedure describes the method used .to check the accuracy of

various ranges of self-reading pocket dosimeters.

PRINCIPLE:

Several dosimeters of a given range are irradiated at a predetermineddistance for a known time from a gamma source. The dose rate atthis distance was determined by using a R-Meter whose calibrationis traceable to NBS. After being exposed to a known dose, thedosimeters are checked for proper accuracy. In addition, thedosimeters are set aside in a radiation free location for 24 hoursto check for drift.

NEEDED EQUIPMENT:

o Instrument Calibration- Tech/Ops Model 773CS-1 3 7 @ (b)(I)(b)(7)(F) I@ on 6-29-83Souce S S-433 IOutput ).0522 r/hr. @ 1 meter 7/-

o Victoreen- Condenser R-Meter Model 570

o Dosimeter Calibration board w/geometric jig for instrumentcalibrator

o Documented dose rate from calibrator to dosimeters

o Various range pocket dosimeters

o "Dosimeter Test Record"

o Stop watch accurate to the nearest .01 second

PRECAUTIONS:

o Use normal precautions utilizing the Tech/Ops calibrator.

o Personnel monitoring required.

Page 2POCKET DOSIMETER ACCURACY/LEAK TEST

PRECAUTIONS continued...

o The drift check (leak test) may be performed prior to orat the completion of the accuracy test.

LIMIT VALUES:

o Accuracy test result should be within -10% to +20% of thetrue exposure.

o Leak test result should not exceed +10% of full scaleduring a 24 hour period.

o All dosimeters calibrated on 6 months interval.

USER INSTRUCTIONS:

***Drift Test***

1. Zero dosimeters to remove static charge.

2. Record serial numbers and initial reading on recordform.

3. Place dosimeters in a low background area and allowto sit for 24 hours.

4. Record the 24 hour reading, then calculate the differenceand per cent error.

***Accuracy Check***

1. Record initial reading, then place dosimeters oncalibration jig.

2. Expose one range at a time and exposure long enoughto give a reading of 2/3 to 3/4 of scale range.

3. Stop exposure and record final reading. Calculatedifference and per cent error.

4. Following completion o.f drift and accuracy test, placea dated calibration sticker on each dosimeter.

5. Complete a "Pocket Dosimeter Test Record" form oneach dosimeter tested.

HALLIBURTON SERVICES

DAILY DO S I M E T E R R E A D I N.G

NAME DOSIMETER DOSIMETER TOTALSERIAL READING DOSE

SOCIAL SECURITY I DATE NUMBER IN MREM REC'D

DATE OF BIRTHSTART FINISH

MONDAY

TUESDAY

WEDNESDAY

THURSDAY

FRIDAY

SATURDAY

SUNDAY

TOTAL DOSE RECEIVED

PERSON COMPLETING REPORT

DATE

A

* TRC FORM 21-3 PVO l3LA ,-A V (LC-• o lOz•S 4 L.d/9' -L M-- * ,C 0 ,: r , . ( ir

(77)Texas Department of Health

CURRENT OCCUPATIONAL EXTERNAL RADIATION EXPOSURE(See Instructions)

Identification

1. NAME (Print--Last, First and Middle) 2. SOCIAL SECURITY NO.

3. DATE OF BIRTH (Month, Day, Year) 4. NAME OF LICENSEE OR REGISTRANT

Occupational Exposure

5. DOSE RECORDED FOR (Specify: 6. WHOLE BODY DOSE 7. METHOD OF MONITORING (e.g.,Whole body; skin of whole body; STATUS (rem) Film Badge--FB; Pockethands and forearms; feet Chamber--PC; Calculations--and ankles). Calc.)

X or GAMMA BETA

NEUTRONS

8. PERIOD OF EXPOSURE Dose for the Period (rem) 13. RUNNING TOTAl(From--To) 9.. X or 10. BETA 11. NEUTRON 12. TOTAL FOR CALENDAR

GAMMA QUARTER (rem)

Lifetime Accumulated Dose

14. PREVIOUS 15. TOTAL 16. TOTAL ACCUMU- 17. PERM. ACC. 18. UNUSED PARTTOTAL QUA;TERLY LATED DOSE DOSE 5(N-18) OF PERMISSIBLE(rem) DOSE (rem) (rem) ACCUMULATED

date rem DOSE (rem)

(

21-52

S11 ,LLIBURTON SERVICESDRAWER 1431 DUNCAN. OKLAHOMA 73533

DEPARTMENT OF GOVERNMENT REGULATIONS

RON BECHTEL

Manager

Writer's Direct Dial Number

POCKET DOSIMETER TEST RECORD

DOSIMETER R-_NGE:

Leak Test Limits Accuracy Check Limits

±1 0 % of FULL Scale - 10% TO + 20% Of EXPOSURE

EXPOSURE = ( ziR/hour) (T1ME OFF: DATE OFF:TIME ON: DATE ON:

HOURS EXPOSED

hours-exp;osed.) =mR.

hours

- For Co 6 0 Source use 5.26 Years, for Cs1 3 7 Source use 30.2 Years

,LEA.K TEST i SOURCE TEST * ***********SERIAL REDNS DELTA jRANSjDETFNUmBER ON! OFF READ IG or- ON I OFF REvADING Ir -[ REM", S

I J7 J_____ I _ ____ II I I

_____ I __ I I __-

____________ I ____ 1 ______ I ___________ J . -.[___________ i

I II ____ I

II- I --

CO>'.PLETLD BY:

G A Halliburlon Comrpny

ATTACHMENT #5

The Halliburton Services Research Center, Duncan,Oklahoma has committed laboratory module, number B311 toserve solely for radioactive research. This module housesthe Canberra Multichannel Analyzer with the shielded NaIdetector system. A Ludlum Model 2200 Scaler with a Model44-9 Pancake GM Probe for portability is also maintained atthis site. The two fume hoods systems were manufactured byKewanee. One is an eight (8) foot hood with a 1440 cfm facevelocity, the other a six (6) foot hood with a 1070 cfm facevelocity.

Anticontamination clothing including, boot covers, zipfront coveralls, gloves and hoods are furnished for personnelas needed. Posi-Grip tong 30", 36" and 42", are available.Respirators with disposable charcoal filters are available asneeded.

The attached drawings or sketches of the RAYFRAC®Manufacturing area and the RAYFRAC® building.

(b)(4)

(b)(4)

1~

STEPHEN EARL HOOK

(b)(6)

Education:

Southeastern Louisiana University bB. S. Biological Sciences, Secondarý"Educati6

Employment History:

October 1983 - Present

Present Duties:

June 1975 - October 1983

Duties Included:

Radiation Safety OfficerHalliburton Services

All aspects of Radiation Safetyincluding handling, use, trans-portation, and training. Dutiesalso include periodic internalinspections and investigationswhen needed.

Health PhysicistLouisiana Nuclear Energy Division

Supervision of Radioactive MaterialProgram which included both licensingand inspection. Assisted in thecoordination of a statewide regula-tory program.

Continuing Education Training Courses:

December 1975, "Advanced Medical X-Ray Inspection Procedures",(one week), Baylor Medical School, Houston, Texas

February 1976, "Health Physics and Radiation Protection", (tenweeks), Oak Ridge Associated Universities, Oak Ridge, Tennessee

January 1977, "Gas and Oil Well Logging for RegulatoryPersonnel", (one week), Schlumberger Well Logging Services,Houston, Texas

May 1977, "Industrial Radiography for State RegulatoryPersonnel", (one week), Louisiana State University, BatonRouge, Louisiana

July 1977, "Medical Uses of Radionuclides for RegulatoryPersonnel", (One week), Baylor Medical School, Houston; Texas-

June 1978, "Inspection Procedures", (one week), NuclearRegulatory Commission, Region 3, Glen Ellyn, Illinois

STEPHEN EARL HOOK(continued)

August 1978, "Medical X-Ray Quality Assurance", (one week),Bureau of Radiological Health, Rockville, Maryland

September 1979, "Orientation to Regulatory Practices", (twoweeks), Nuclear Regulatory Commission Headquarters, SilverSprings, Maryland

August 1980, "Radiation-Protection Engineering", (one week),Oak Ridge Associated Universities, Oak Ridge, Tennessee

April 1981, "Verification Measurements on Cobalt-60 Irrad-iators", (three days), M. D. Anderson Hospital and TumorInstitute, Houston, Texas

May 1981, "Radiological Emergency Response Course", (tendays", Reynolds Electric Company, Las Vegas, Nevada

April 1983, "Nuclear Power Plant Off-Site RadiologicalAccident Assessment" (one week), Federal Emergency ManagementAdministration, Portland, Oregon

Invited Presentations:

"Inspection Procedures", NRC Industrial Radiography CourseInspectors, Louisiana State University, June 1979

"Industrial Radiography Regulations and Licensing", NRCIndustrial Radiography Course for State Inspectors, GammaIndustries, Baton Rouge, Louisiana, June, July, August, 1982

"Radiographer Certification and Testing", Non-DestructiveManagement Association Annual Meeting, Las Vegas, Nevada,February 1982

"Industrial Radiography and Well Logging Inspection Procedures",NRC Inspection Procedures Course for State Inspectors, Atlanta,Georgia., July & August, 1982 and August, 1983

"Industrial Radiography Licensing Procedures", NRC Orientationto Regulatory Practices, Bethesda, Maryland,: September 1982and September 1983

"Contamination in the Oil Field with Ir-192", Bureau ofRadiological Health, Region IV Meeting, Shreveport, Louisiana,October, 1982

STEPHEN EARL HOOK(continued)

Publications:

A Survey of the Uses of Radioactive Materials in Louisiana'sOffshore Waters, NUREG/CR-3516, Co-Author, November 1, 1983.

Professional Organizations:

Health Physics SocietyDeep South Chapter, Health Physics SocietyConference of Radiation Control Program Directors, Inc.

Military Service:(b)(6)

RUSUME' OF DANNY G. KELLY

EDUCATION:

EXPERIENCE:

Southwestern Oklahoma State Universit'..Weatherford, Oklahoma, BS, Chemistry,(b)(6)

Received extensive instruction and information onradiation, health safety, isotope applications,etc. from Mr. R. George Mihram, Radiation SafetyOfficer during the years 1964, 1965 and 1966.

1955 - 1962: C AnalyticalSection, Chemical Research and Development.Duties included such activities as:

Mineral identification and analysis byPetrographical microscopic and x-ray diffractiontechniques.

Chemical analysis and development of analyticalprocedures for ferrous and non-ferrous metals.

Chemical analysis of waters, brines and aqueouseffluents, such a chemical plant effluents, minewaste water, etc.

A member of an API Water Study Committee with thepurpose of developing, establishing andrecommending analytical procedures for oil fieldbrine analysis 1958 - 1968.

1963 - 1965; Development ChemistAnalytical procedures development for chemicaland physical testing of crude oils and refinedpetroleum products.

Development of analytical procedures for qualitycontrol and chemical monitoring of industrialcleaning chemicals and solvents.

Evaluation of isotope concentration and gammalogging equipment made for fracture model study.

Received extensive training in the actual use ofradioisotopes in field activities. This includedthe use of RAYFRAC proppants, RAC-2 and RAC-3,mixing, blending, displacement into theformation, and health safety surveys uponcompletion of the operations.

1965 - 1974, Group Leader; General AnalyticalGroup, Chemical Research and Development.Duties include all supervision of such activitiesas:

16~985

-2-

Those stated above.

Instrumental methods of analysis and proceduredevelopment including:

Atomic Absorption SpectroscopyInfrared SpectroscopyGas ChromatographyX-ray DiffractometryScintillation Counting Equipment

Radioactive rpsearch and field serviceactivities. Research included such projects as:

Evaluation of isotopes and techniques fortracing of waterflood systems.

Chemical cleaning and decontamination ofnuclear reactors. This involved theselection of a chemical solvent as well astreatment and disposal of the chemicalwaste.

1974 - 1976; Radiation Safety Officer forHalliburton Services.

Assumed all duties and responsibilities of thisoffice in compliance with NRC Regulations.

1976 - 1978, Manager; Middle East TechnicalCenter, Manama, Bahrain.

Responsible for the supervision of all TechnicalCenter activities for the Middle East Region ofHalliburton Limited in Bahrain. Providedtechnical testing and advisement with allproducts and services of Halliburton.

1978 - 1979, Research Chemist with projectassignments of solvent system development fordecontamination of the primary side of heatexchange in nuclear reactors.

Responsible for compiling and writing analyticalprocedures for monitoring chemical solventsdesigned to remove water formed and corrosionproducts from industrial equipment. Writing anddesigning technical data sheets for HalliburtonServices products and processes used in chemicalcleaning of industrial and process equipment.

1980 - Present - Radiation Safety Officer;Regulatory Specialist in the GovernmentRegulations Department of Halliburton Services,Duncan, Oklahoma.

-3-

April 14 - 18, 1980 - Attended the "RadiationSafety Specialist Training Program" conducted byOklahoma State University, Howard M. Johnson,Ph.D., Instructor.

Thorough knowledge of CFR, Titles 10 and 49 andall Agreement States regulations governingradiation control. Responsibilities includepreparation of license applications for newradioactive material license as well as licenserenewal.

Develop procedures and techniques for inventorycontrol of radioactive material for more than 200District Camps within the USA, to assurecompliance with NRC and Agreement States regu-lations.

Conducting of Radiation Safety Training Schoolsthroughout Halliburton Services domestic op-erations:

The schools are designed to give field personnela thorough understanding and knowledge of basicapplied physics, the actual field handling anduse of radioisotopes, and radiological healthsurveys of location and personnel for healthsafety. Primarily those receiving instructionare graduate engineers for Halliburton, Servicesfield operations.

Compiled and edited the "Radiation Safety Manual"used by Halliburton Services and HalliburtonIndustrial Services, Inc., both HalliburtonCompanies.

Provide health physicist advise, instruction,remote handling devices, protective clothing,survey and measuring equipment for all fieldlocations as well as X-ray inspection personneland nuclear reactor decontamination teams.

Maintain all records relating to procurement,storage, transport, usage, waste disposal andapplications of radioactive materials for bothdomestic and international operations.

Consultation with Research for product, processand equipment development and design relative tonuclear facility decontamination and oil fieldtracer services.

-4-

Advisement to field service Engineering fortracer applications including isotope andequipment selection on routine and specialityprocesses as well as consultation with customersfor tracer sales and speciality processesemploying radioactive materials.

Qualifications of Texas Radiation Control PersonnelTexas Department of Health

Richard A. Leonardi, Jr.

A. Formal Education: I(b)6)

-Grayson County Junior College, 64 hours-University of Texas at Arlington, 13 hours-Texas Christian University, 28 hours-Southeastern OkI-1honm') State University, B.S. Degree, Biology and

Chemi stry, (b)(6)

-Health Physics i-.Tndldiation Protection Course, February/J___)Oak Ridge Associatcd Universities, Oak Ridge, Tcnnes7e, loweeks

-Tyler Junior College, Petroleum Technology, currently enrolled

B. Short Courses:

U.S. Army Course:

2-week Medical X-ray Survey Techniques

Nuclear Regulatory Commission Courses:

1-week Medical Use of Radionuclides for State Regulatory Personnel1-week Inspection Procedures CourseI-week Safety Aspects.of Industrial Radiography for State Regula-

tory Personnel2-week Radiological Emergency Response Operations Course

2-week Orientation Course on Regulatory Practice and ProceduresCourse

1-week "Gas and Oil Well Loggi.ng for Regulatory Personnel." Course

I-week "Tel~therapy Calibration Procedures Course"

Bureau of Radiological Health Courses:

2-week Basic Course for investigators - D)iagnostic X-ray Survey

C. Associations:

Member, National-Health Physics SocietyMember, Health Physics Society, South Texas ChapterMember, The Texas Public Hcalth Association AssociationRegistered, Professional Sanitarian of Texas

-1,;85

Page 2

D. 514 years as the Administrator of the Radiation Control Branch ofthe Texas Department of Health, Division of Occupational Healthand Radiation Control in Public Health Regions 7 and 10, covering38 counties in East and Southeast Texas. I have been responsiblefor the Administration of all compliance activities includingroutine inspections and special investigations. I have super-vised the training of inspection trainees in Regions 7 and 10 ona full time basis. I supervised the training both x-ray and ra-dioactive material inspectors.

Perform radiation detection training for local police and fire depart-ment's and demonstrate the proper use, care, and handling of radia-tion detection instruments.

Have logged over 300 hours of reactor health physics experience as Iparticipated in the initial recovery operation at the Three Mile Is-land (TMI) nuclear facility from May 18, through June 11, 1979, afterthe unfortunate accident on March 28, 1979. A month's vacation leavefrom the Texas department of Health obtained and 1 joined a privateTMI contractor, Nuclear Support toward the recovery efforts in theTMI Auxilinry Building. I worked with several other Health Physicistin operating an access control point leading into the badly contam-inated auxiliary building. Duties included:

Performance of routine physical radiation surveys and smear radiationsurveys in the auxiliary building.

Supervised the processing and insured that proper safety equipmentand Anti-C clothing were being worn by the skilled craft workersgoing into the airborne contaminated auxiliary building.

Escorted workers and Nuclear Regulatory Inspectors into high radia-tion area and highly contaminated area within the auxiliary building.

Current Address:

. chard A. Leonard..

(b)(6)

f '

N

EXPERIENCE SUMMARY

1. Texas Department- of Health, Division of Occupational Health &Radiation Control, Tyler, Texas

5k years as the Administrator of the Radiation Control Branch ofthe Texas Department of Health, Division of Occupational Healthand Radiation Control in Public Health Region 7 & 10, covering 38counties in East and Southeast,Texas. I have been responsiblefor the administration of all compliance activities includingroutine inspections and special investigations. I have super-vised the training of inspector trainees in Regions 7 & 10 on afull time basis. I supervise the training of both x-ray and ra-dioactive material inspectors.

2. Safeway Stores, Inc., Brookside Division Plant (Supply Division),Denison, Texas

I have served in the capacity as both Plant Chemist and QualityControl Supervisor for the intraplant departments of Margarine,Shortening, Dressings, and Household Chemical Plant for SafewayStores, Inc., Brookside Division, Denison, Texas. I am familiarwith all lab equipment, statistical quality control methods, sani-tation and all company policies related to an FDA regulated en-vironment.

I supervised all quality control functions for the Margarine,Shortening, and Household Chemical departments. I was respon-sible for twelve quality control inspectors on a two shift basis,dalIy, weekly, and monthly quality control reports, inspection ofraw materials, packaging specifications, formulation, and pro-cessing audits, sanitation inspection and report, plus inter-facing with upper plant and staff management personnel, includingpurchasing, industrial engineering, production, accounting, andpersonnel.

3. Safeway Stgres, Inc., Retail Stores (Grand Prairie, Ft. Worth, &Lubbock, Texas)

I worked in four different Safeway Stores as a heavy duty checker-

-stocker during my college undergraduate work.

4. Summit Oaks Achievement Center, Laneville, Texas

Summit Oaks is a state licensed private treatment center for boysandgirls emotionally disturbed or with maladjusted behavior. Iserved as a Couselor and later a Senior Child Care Staff member.I coordinated and supervised recreational activities and laterserved as a House Parent for thirty-two children.

Addendum

March 1983 - Present: Radiation Safety Officer withHalliburton Services, Tyler, Texas. Present duties andresponsibilities include the entire radiation safetyprogram and management of radioactive materials in twentyHalliburton Districts in the North Texas Area, and BossierCity and Haynesville, Louisiana. Established the radioactivematerials management program for Halliburton Districts inthe State of New Mexico.

Has thorough knowledge and experience in the oil fieldservice industry.