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DEFENSE LOGISTICS AGENCYHEADQUARTERS

CAMERON STATIONALEXANDRIA. VIRGINIA 22304-6 100

IN REPLY

REFER TO DLA-WH 2 4 JAN R6~

/

SUBJECT: Application for Consolidated US Nuclear Regulatory Commission (NRC)Material License

TO: CommanderUS Army Communications and Electronics CommandATTN: AMSEL-SF-MR

1. We have reviewed the subject draft NRC license application and concur withit in its entirety.

2. No comments or changes are required.

FOR THE DIRECTOR:

ChiefSafety and Health Divi~ion

C&eqIF

DEPARTMENT OF THE ARMYUNITED STATES ARMY MISSILE COMMAND

REDSTONE ARSENAL, ALABAMA 35898-5000

REPLY TOATTENTION OF

AMSMI-SF 7 March 1986

SUBJECT: Application for Consolidated U.S. Nuclear RegulatoryCommission (NRC) License

CommanderU.S. Army Communications-Electronics Commandand Fort MonmouthATTN: AMSEL-SF-MRFort Monmouth, New Jersey 07703-5000

1. References:

a. Letter, AMSEL-SF-MR, 3 January 1986, subject as above.

b. Letter, AMSEL-SF-MR, 13 February 1986, subject as above.

2. This office concurs with the license application forwarded with reference a.with the changes identified in reference b.

3. MICOM - Providing.Leaders the Decisive Edge.

FOR THE COMMANDER:

FRANCIS E. AARTChief, Safety Office

AN EQUAL OPPORTUNITY EMPLOYER

t~ii 1(1

, DEPARTMENT OF THE ARMYUNITED STATES ARMY TANK-AUTOMOTIVE COMMAND

WARREN. MICHIGAN 48090

REPLY TO

ATTENTION OF

AMSTA-CZ 4-March 1986

SUBJECT: Application for US Nuclear Regulatory Commission (NRC) License

CommanderHQ, US Army Communications -

Electronics Command and Ft. MonmouthATTN: AMSEL-SF-MRFt. Monmouth, NJ 07703-5000

1. Reference letter, AMSEL-SF-MR, CECOM, dated 18 February 1986, SAB.

2. This command concurs with the NRC license based upon the comments givenper referenced letter.

FOR THE COMMANDER:

r ICHARD M. GRNYASafety Director

o')1 / /1

DEPARTMENT OF THE ARMYHEADQUARTERS. US ARMY ARMAMENT. MUNITIONS AND CHEMICAL COMMAND

ROCK ISLAND. ILLINOIS 6 1290-6000

REPLY TO

AT"ENTIONr OF:

AMSMC-SFS

SUBJECT: NRC License Application - CECOM 21 MAR 1986

CommanderHQ, CommunicationsATTN: AMSEL-SF-MRFt. Monmouth, NJ

Electronics Command(Mr. Santarsiero)

07703

1. Reference FONECON between Mr. Santarsiero, AMSEL-SF-MR, and Mrs. LaFrenz,AMSMC-SFS, 28 Feb 86, SAB.

2. As discussed in referenced FONECON, this headquarters has reevaluated therequirements of subject application that apply to HQ, AMCCOM. Thisheadquarters concurs with subject license application.

3. POC is Mrs. Katheryn LaFrenz, AV 793-2966.

4. AMCCOM - Providing Leaders the Decisive Edge.

FOR THE COMMANDER:

DAVID P. SKOMACh, Systems, Chemical & Radiation Div

DEPARTMENT OF THE ARMYHEADQUARTERS, US ARMY AVIATION SYSTEMS COMMAND

4300 GOODFELLOW BOULEVARD, ST. LOUIS, MO. 63120-1798

REPLY TOATTENTION OF

2 0 FEB 19866AMSAV-X

SUBJECT: Application for Consolidated. U.S. Nuclear Regulatory Commission (NRC)License

CommanderU.S. Army Communications-Electronics CommandATTN: AMSEL-SF-MRFort Monmouth, NJ 07703-5000

1. AVSCOM concurs with the subject application subject to changes reflectedon the attached enclosure.

2. The Statement of Work (SOW) and associated CDRL which was provided by

your office has been incorporated into applicable contracts involvingthorium-fluoride coated optics. If license changes impose additionalrequirements request that an updated SOW and CDRL be provided this officefor inclusion in future contracts. This action will assure compliance ofAVSCOM procured items with your license requirements.

3. AVSCOM - Providing Leaders the Decisive Edge.

FOR THE COMMANDER:

Encl2/?4 i6i'?.

(NORBERT R. KNIEPP*Acting ChiefSafety Office

L5;ýi6i /-)

DEPARTMENT OF THE ARMYHEADQUARTERS, US ARMY COMMUNICATIONS-ELECTRONICS COMMAND

AND FORT MONMOUTH

FORT MONMOUTH, NEW JERSEY 07703-5000REPLY TO

ATTENTION OF

AMSEL-SF-41 11 March 1986

MEMORANDUM FOR RECORD

SUBJECT: Application for Consolidated U.S. Nuclear RegulatoryCcmmission (NRC) License

1. Reference:

a. Letter, AMSAV-X, 20 February 1986, subject as above.

b. FONECON between Mr. Dennis Chambers, U.S. Army Aviation Systems Commandand Mr. Joseph M. Santarsiero, CECOM Safety Office, 11 March 1986, subject asabove.

2. Reference la provided concurrence to subject license application contingentupon four suggestions/recommendations provided.

3. During reference lb FONECON, indication was made that two of the foursuggestions/recommendations provided would not be incorporated into subjectlicense application. The considerations provided do not reflect this command'sradiation protection policy relating to Depot Radiation Protection Officertraining requirements and the incorporation of Environmental Assessmentdocumentation in NRC license application,.

Prepared by: A .3

R b Health y:cist

Reviewed by: _ -

BARRY ~4 i L. ORC, Radiodal Sfty Engr Br

STEVEN A. HOActing Chief, Safety Office

Approved by:

CF: Cdr, AMSAV-X

SUPPLEMENT A

1 Reference: Item 3, NRC Form 313.

2. The radioactive material shall be utilized under the supervision of Depart-

ment of the Army (DA) military and/or civilian personnel by US Department of

Defense (DOD) installations/activities at worldwide locations.

Page l.of 1 Supplement A

1. Reference: Item

A. Cobalt-60

SUPPLEMENT B

5, NRC Form 313.

A

CiB. Cesium-137

C. Strontium-90

D. Strontium-90

E. Strontium-90

F. Strontium-90

G. Plutonium-239

H. Plutonium-239

I. Cobalt-60

J. Plutonium-239

K. Thorium-230

L. Thorium-232

I

[.

LD. 45 mCi (NTE 150 microcuries(uCi) per source)

(

F. Sealed SNo. 12- 19 21-

G. Solid f(Electropla

H. Solid fbutyral res

•ources (3M Dwg F. 18 mCi (NTE 36 uCi per0474-8) source)

orm G. 0.0115 grams (gm)ted metal) (NTE 23 micrograms (ugm)

(1.4 uCi) per set)

orm (Polyvinyl H. 0.246 gm (NTE 819 ugmin) (50.3 uCi) per set)

Instrument Corp. J. 1 gm (NTE 10 nanocuries(nCi) per source)

Instrument Corp. K. 1 milligram (mgm) (NTE 20nCi per source)

Research Corp. L. 2.76 kilograms (Kgm) (NTEB-1093 300 nCi per source)

Page 1 of 10 Supplement B

LJ. EberlineModel CS-I

K. EberlineModel CS-12

L. NuclearModel No. E

M. Krypton-85

N. Thorium-232

M. Sealed Sources (USAEADwg No. B124-12-8).

N. Solid form Thorium-232Fluoride coating on opticalsystems.

M. 120 Ci (NTE 6 mCi per source)

N. 40 Kgm (NTE 2 gm (0.218 uCi)Thorium per optical system)

0. Arrericium-2'41 M. Sealed Sources (Amersham 0. 50 mCi (Five sources ofRadiochemical Center, 10 mCi each)Amersham Code 2084)


2. SOURCE DESCRIPTIONS

A. and B.: AN/UDM-1 and AN/UDM-1A Radiac Calibrator Sets:

/.

(3) The sources are manufactured in accordance with (IAW) the require-

ments set forth in Military Specification MIL-R-16131A (SHIPS) (Enclosure 5),

MIL-C-22211A (EC) (Enclosure 6), Bureau of Ships Dwg No. A-9339-F (Enclosure 7)

and AB-9394-B (Enclosure 8).

(4) All sealed sources are manufactured as special form material IAW US

Department of Transportation (DOT) regulations, Title 49, Chapter 1, Code of

Federal Regulations (CFR) and International Atomic Energy Agency (IAEA) stan-

dards. The IAEA Certificate of Competent Authority for the Gamma Industries

Type VD-HP sealed source capsule is found at Enclosure 9. A data sheet on spe-

cial form capsule testing and sealed source certification for the JLS Type 6810

sealed source capsule are found at Enclosures 10 and 11.

(5) The above sources appear in the Approved Sources and Devices Catalog

of the US Nuclear Regulatory Commission (NRC).

Page 3 Of iOti Supplemqnt B

C., D., E. and F.: AN/UDM-2 Radiac Calibrator Set:

(1) The sealed sources incorporated in the AN/UDM-2 Radiac Calibrator

Sets utilize Strontium-90 (Sr-90) and have been manufactured by various corpora-

tions as special form material IAW applicable drawing numbers and DOT/IAEA

requirements. For the purpose of explanation, these sources are designated

Sources A, B, C and D:

(a)

(b) Source B: Sealed sources NTE 150 uCi per source, 45 mCi total.

(c) L

(d) Source D: Sealed sources NTE 36 uCi per source, 18 mCi total.

Based on the useful lifetime of the sealed sources, new sources are being procu-

red for refurbishment of all calibrator sets. The AN/UDM-2 Radiac Calibrator

Sets incorporating the original sources, i.e., sources A and B, will be stored

at Lexington-Blue Grass Army Depot (LBAD), Lexington, KY, and/or Sacramento Army

Depot (SAAD), Sacramento, CA, until disposal can be accomplished. The newly

procured sources C and D, are/will be incorporated within all AN/UDM-2 Radiac

Calibrator Sets utilized by DA installations and activities worldwide.

(2) Sources A and B were manufactured by Gamma Industries, Inc., and

Gulf Nuclear, Inc. IAW requirements set forth in Military Specification MIL-R-

55350 (EL) (Enclosure 12) and ECOM Dwg No. SM-B-509048 and SM-B-509057 (Enclosu-

res 13 and 14) and procedures described below:


(a) Gamma Industries, Inc., Houston, Texas: A Corning Glass Company

vycor porous disk is immersed into a Sr-90 Oxide aqueous solution in order to

enable sufficient radioactive material to penetrate into the disk. The disk is

then dried and fired at elevated temperatures in order to insure that the pores

shrink or collapse around the radioactive material thus sealing the pores.

(b) Gulf Nuclear, Inc. (formerly Nuclear Environmental Engineering"

Inc.) Houston, Texas: Union Carbide Corporation, Linde Division, Type AW-500

molecular sieves compressed into disk or pellet form, are immersed into a Sr-90

Nitrate aqueous solution to form strontium calcium aluminum silicate. To insure

that the Sr-90 remains, the molecular sieve is dried at elevated temperatures.

(3) Sources C and D have been manufactured by the 3M Company, New Brigh-

ton, Minnesota and designated Model Number 3F1G. The IAEA Certificate of

Competent Authority for the 3M Company Model 3F1G is provided at enclosure 15.

The Sr-90 contained in these sources are chemically combined with a ceramic base

which is then fired to produce "microspheres" of controlled shape and particle

size. This provides for an extra factor of safety in addition to the safety

factors already provided by the double encapsulation and special form testing

requirements. These sources are manufactured IAW Military Specification MIL-R-

55350A(ER) (Enclosure 16) and 3M Dwg No. 12-1921-0474-8 (Enclosure 17).

G. AN/UDM-6 Radiac Calibrator Set: The AN/UDM-6 Radiac Calibrator Set is

the military version of the commercially available Eberline Instrument Corpor-

ation (EIC) Model S94-I Calibrator Set and utilizes approximately 23 ugm (1.4

uCi) of Pu-239. The calibrator set consists of four cast aluminum source jigs

each containing one Pu-239 source. The Pu-239 is electroplated onto 1-1/4 inch

diameter stainless steel or nickel disks with a one inch diameter active area.


A solution containing a known quantity of Pu-239 Nitrate is utilized in the

electroplating process. The sources are dried and fired at elevated tempera-

tures to assure the adherence of the radioactive material. One hundred percent

of the radioactive source disks are tested by the manufacturer for adherence by

applying masking tape directly onto the active area. The masking tape is remo-

ved and the adhesive side analyzed for removable contamination. As specified by

EIC, adherence-criteria requires that no more than 0.01 percent of the active

material be removed for the source to pass the adherence test.

H. AN/UDM-7C Radiac Calibrator Set:

(1) Enclosure 18 is Military Specification, MIL-R-24265 (SHIPS) used for

the manufacture of the AN/UDM-7C Radiac Calibrator Set which contain two each

sources of Pu-239, one source of 810 ugm (49.8 uCi) and one source of 8.1 ugm

(0.5 uCi). A solution containing a known quantity of Pu-239 Chloride is mixed,

with a polyvinyl-butyral resin and 99 percent ethyl alcohol mixture to assure a

uniform dispersion of the radioactive material in the solution. This solution

is then poured onto a 12-1/2 inch diameter cast acrylic plastic disk and is

allowed to dry under controlled conditions to produce a very thinly deposited

layer of resin having a high degree of uniformity.

(2) One hundred percent of the radioactive source disks were tested by

the manufacturer for uniformity requirements prior to assembly into its shelf

casing. One hundred percent of the sources were also tested for accuracy and

leakage requirements in their completed configuration. In addition, a random

sampling of ten percent of the completed AN/UDM-7C Radiac Calibrator Sets were

tested for uniformity, accuracy, shock, vibration, and leakage requirements and

witnessed by a Government representative. The aforementioned testing require-

Page .6 of 10 Sp~e~nSupplemeTit B

ments are stipulated in Enclosure 18. Enclosures 19, 20, 21 and 22 are the

engineering drawings detailing the construction of the AN/UDM-7C Radiac Calibra-

tor Set.

I. M3A1 Radioactive Source Set: The doubly encapsulated sealed sources are

manufactured IAW Military Specification MIL-R-51081A (MU), Radioactive Source,

Cobalt-60, Gamma, MIAl, and MIL-R-51080A (MU), Radioactive Source Set, M3A1;

Gulf Nuclear, Inc. Dwg No. A-5001; and USAEA Dwg No. C124-10-34 (Enclosures 23,

24, 25 and 26). Initial source activity will be 100 mCi + 30 percent. US Army

Chemical Corps Dwg No. C124-10-10, C124-10-13, and D124-0-2, (Enclosures 27, 28

and 29) describe the specifications of the component parts, i.e., the MIAl

source assembly, disc assembly and shield assembly

J. CS-I Check Source:

Approximately 10 nCi of Pu-239 is used in the manufacture of the EIC

Model CS-i check source. The source is rectangular in shape and has a centered

recessed circular area into which aqueous Pu-239 Nitrate has been deposited,

dried and fired at elevated temperatures. The sources are checked by EIC for

adherence by applying masking tape directly on the active area of the sources.

The masking tape is then removed from the source and the adhesive side of the

tape is checked for any removable contamination. EIC requires that no more than,

0.1 percent of the radioactive material be removed from the source to pass the

adherence test. A decal identifying the radionuclide, activity and date of man-

ufacture is placed on the surface opposite the recessed area.

K. CS-12 Check Source: The EIC Model CS-12 check source utilizes less than

20 nCi of Thorium-230 (Th-230). The Th-230 is electroplated onto a 0.875 inch


diameter steel disc and is then epoxyed into a 2 inch diameter plastic disc.

L. B-1093 Check Source: The Nuclear Research Corp. B-1093 check source

contains less than 300 nCi Th-232 and is manufactured by rolling and extruding

Th-232 metal into sheet form. The source is 2.25 inch by 0.515 inch by 0.010

inch in dimension and weighs approximately 2.15 gins.

M. MX-7338/PDR-27( ) Radioactive Test Sample: Approximately 6 mCi of Kryp-

ton-85 (Kr-85), as a sealed source, is utilized in the MX-7338/PDR-27( )

Radioactive Test Sample. The sealed sources are manufactured IAW Military

Specification MIL-R-51305(MU), Radioactive Test Sample, Krypton 85, MX-7338/PDR-

27( ) and USAEA Dwg No. C124-12-6 (Enclosures 30 and 31). USAEA Dwg No. B124-12-

7, B124-12-8, B124-12-9, and B124-12-10 (Enclosures 32, 33, 34, and 35) describe

the specifications of the component parts, i.e., the aluminum body (source hous-

ing), copper source capsule, aluminum source .housing plug and-identification tag

for the Radioactive Test Sample. Quality Assurance (QA) and performance testing

of MX-7338/PDR-27( ) Radioactive Test Sample procurements are-identified at Sup-

plement G.

N. Thorium-232 Fluoride (ThF 4) Optical Coating in Thermal Imaging Night

Vision Devices (NVD). ThF4 in solid form (approximately 75.4 percent by weight

Thorium), is utilized as multi-layer anti-reflective (MLAR) optical coatings on

thermal imaging lenses of the Forward Looking Infrared (FLIR) systems, (i.e.,

NVD's). The Army QA program for all MLAR coatings of Infra-red (IR) optical

elements is described at Supplement G.


0. Americium-241 Variable Energy X-ray Source (VEX Source):

(1) The VEX Source, Model AMC 2084, as supplied by Amersham Corpor-

ation, Arlington Heights, IL., incorporates Am-241, maximum activity 10 mCi per

source, as an oxide chemical constituent of a ceramic enamel bonded to stainless

steel with integral tungsten alloy rear shielding. The primary annular source

is described in Amersham Radiochemical Centre (ARC) drawings 10040 and 10048

(Enclosures 36 and 37) with the completed assembly shown at Enclosure 38 (Amers-

ham Code (AMC) 2084). The source has been subjected to and passed the American

National Standards Institute (ANSI) C64344 Sealed Radioactive Source Classific-

ation tests for source integrity (Enclosure 39 and 40), and has been

successfully tested for IAEA special form material approval (Enclosure 41 and

42). Leak test procedures, as identified at Enclosure 43, are performed on each

production source prior to attaching the target assembly.

(2) To further verify the sealed source integrity of the Amersham Model

AMC 2084 Am-241 VEX Source, the source was subjected to various environmental

testing procedures performed at the Environmental Test Facility of the Technical

Support Activity (TSA) formally assigned to the US Army Electronics Research and

Development Command and now transitioned to CECOM. Test procedures included

immersion, high and low temperature extremes, altitude, vibration and drop test-

ing. Before commencing, and at the termination of each test procedure, the VEX

Source utilized (Serial No. 3842-LA) was dry and wet wipe tested for the pres-

ence of removable contamination. The wipes were evaluated utilizing a Tennelec

LB 5100 Series II Automated Low Background Alpha/Beta Counting System (Minimum

Detectable Activity (MDA) of 0.58 picocuries (pCi) for alpha radiation at a 95%

confidence level). All wipe tests analyzed were less than MDA and therefore


indicate that the sealed source integrity of the VEX Source had not been brea-

ched. The specific parameters associated with each test procedure and test

results are provided at Enclosure 44.


SUPPLEMENT C

1. Reference: Item 6, Form NRC 313.

Commodity Use Description

AN/UDM- 1Radiac Calibrator Set

AN/UDM- IARadiac Calibrator Set

AN/UDM-2Radiac Calibrator Set

AN/UDM-6Radiac Calibrator Set

AN/UDM-7CRadiac Calibrator Set

M3A1 Radioactive SourceSet

CS-I Check Source

CS-12 Check Source

B-1093 CheckSou rce

MX-7338/PDR-27( )Radioactive Test Sample

Calibration of radiationdetection instrumentation

Calibration of radiationdetection instrumentation

Calibration of radiationdetection instrumentationand checking operation ofpocket dosimeters

Calibration of alpharadiation detectioninstrumentation

Calibration of alpharadiation detectioninstrumentation

Calibration of radiationdetection instrumentationand checking operation ofRadiac dosimeters

Operational check of theAN/PDR-60 Radiac Set(alpha detectioninstrument)

Refer Technical Manuel(TM) 11-1176 (Encl 1)

Refer TM(Encl 2)

Refer TM(Encl 3)

Refer TM(Encl 4)

Refer TM(Encl 5)

Refer TM(Encl 6)

11-6665-217-5

11-6665-227-12

11-6665-248-10

11-6665-247- 10

3-6665-214- 13&P

Operational check ofstandard Army alphadetection instruments,equivalent.

or

Operational check of theAN/PDR-56F, standard Armydetection instruments, orequivalent.

Operational check of theAN/PDR-27( ) standardArmy beta-gamma detectioninstrument.

Active area of probeplaced directly overcheck source

Active area of probeplace directly over checksou rce

Check source is bonded tothe underside of theAN/PDR-56F. Operationalstatus of the instrumentis checked by placing theactive probe area direct-ly over the check source

Refer TM 3-6665-264-10(Encl 7)

Page 1 of 2 Supplenent C

Th-232 Fluoride

Am-241 VEX Source

Multi-layer anti-reflectiveoptical coating on thermalimaging devices

Used in conjunction withAN/UDM-7C Radiac Calibra-tor Set for the calibrationof the DT-590/PDR-56F X-rayProbe.

Page 2 of 2 Supplement C

SUPPLEMENT D

1. Reference: Item 7, Form NRC-313.

2. Enclosures 1, 2 and 3 are the qualifications of the U.S. Army Communications-

Electronics Command (CECOM) Radiation Protection Office (RPO), Alternate

RPO and License Manager, respectively.

Page 1 of 1 Supplement D

SUPPLEMENT E

1. Reference: Item 8, NRC Form 313.

2. Radiation Protection Officer.

a. AN/UDM-2, -6, and -7C Radiac Calibrator Sets and Am-241 VEX Source: All

calibration in which the AN/UDM-2, -6, and -7C Radiac Calibrator Sets and Am-241

VEX Source are used will be supervised by a qualified RPO. To be qualified as

such, a person must have received a minimum of 40 hours of formal training in

radiation protection including the following topics:

(1) Principles and practices of radiation protection.

(2) Biological effects of radiation.

(3) Radioactivity measurement and monitoring techniques and instrument-

ation.

(4) Mathematics and calculations basic to the measurement of

radioactivity.

(5) The operation and use of the above radiac calibrator sets/sources.

NOTES

A. Completion of the Radiac Calibrator Custodian Course (Number 4J-Fl/

493-F3) given at the US Army Chemical School, Fort McClellan, AL,

meets these requirements. This course is approved by the US Army

Training and Doctrine Command (TRADOC). The program of instruction

(POI) for this course is provided at Enclosure 1'

Page 1 of 5 Supplement E

B. Where circumstances warrant, equivalent alternate training may be sub-

stituted if this training is approved by Commander, USACECOM, ATTN:

AMSEL-SF-MR, Fort Monmouth, New Jersey 07703-5024. Such training must be

received under the guidance of a qualified RPO, and must include at least 16

hours of actual experience in the use of the radiac calibrator set(s).

b. AN/UDM-1 and -1A Radiac Calibrator Sets and the M3A1 Radioactive Source

Set: All calibration in which the AN/UDM-1 and -1A Radiac Calibrator Sets

and/or the M3A1 Radioactive Source Set are utilized, will be supervised by a

qualified RPO. To be qualified as such, a person must have received a minimum

of 120 hours of formal training in radiation protection to include items (1) -

(4) in paragraph 2a above.

NOTES

A. Completion of the Radiological Safety Course (Number 7K-F3) given

at the US Army Chemical School, Fort McClellan, AL, meets these

requirements. This course is approved by TRADOC. The POI for

this course is provided at Enclosure 2.

B. Where circumstances warrant equivalent alternate formal training may

be substituted if this training is approved by Commander, USACECOM,

ATTN: AMSEL-SF-MR, Fort Monmouth, NJ 07703-5024.

3. Operator or User.

a. AN/UDM-2, -6 and -7C Radiac Calibrator Sets and Am-241 VEX Source: The

operator or user of the AN/UDM-2, -6 and -7C Radiac Calibrator Sets shall have a

minimum of 8 hours training under the guidance of a qualified RPO in the basic

fundamentals of radiological operations, radiac instrumentation, survey techni-


ques and on-the-job training in operation and care of the radiac calibrator.

Instructions shall include safe working practices and inherent hazards associ-

ated with the calibrators.

b. AN/UDM-1 and -1A Radiac Calibrator Sets and the M3A1 Radioactive Source

Set: The operator or user of the AN/UDM-1 and -1A Radiac Calibrator Sets and/or

the M3A1 Radioactive Source Set must have a minimum of 8 hours training under

the guidance of a qualified RPO in the basic fundamentals of radiological opera-

tions, radiae instrumentation, survey techniques and on-the-job training in

operation and care of the calibrator/source sets. Instructions shall include

safe working practices and inherent hazards associated with the calibrators.

4. Radiation Control Officer (RCO). The RCO is an individual appointed by each

major Army command to manage the radiation protection program for the command.

To be qualified as an RCO for the radiac calibrator sets, a person must have a

technical, scientific or engineering background and have successfully completed

a minimum of. 80 hours of formal training in radiation protection including the

topics listed in items (1) - (4) in paragraph 2a above.

5. Maintenance Depot for the AN/UDM-1, -1A, -2, -6, -7C and M3A1 Radiac Cali-

brator/Radioactive Source Sets.

a. Depot Radiation Protection Officer and Alternate(s) must have as a

minimum:

(1) 120 hours of specialized training in radiation protection to in-

clude items listed in (1) - (4) in paragraph 2a above and


(2) A minimum of 2 years experience in radiation protection or

(3) An additional 80 hours training and/or formal course work in

radiation protection.

An individual not meeting these criteria may qualify as RPO only if the 120 hour

criteria has been met and provisions are made to obtain the additional 80 hours

of training within a one year period. An individual not meeting these criteria

may qualify as Alternate RPO only if the 120 hour criteria has been met and pro-

visions are made to obtain the additional 80 hours of training within a two year

period.

b. Technicians. The minimum requirements necessary for persons performing

leak tests on these radiac calibrator sets are the stipulations indicated at

paragraph 3 above with the addition of a minimum of one hour on-the-job training

under a qualified RPO involving instruction in the method of performing the leak

test, e.g., points on the equipment to be smeared and the method of taking the

smear.

6. Bulk Storage Depots. Bulk storage depot RPOs will have a minimum of 120

hours of specialized training in radiation protection to include items listed in

(1) - (4) in paragraph 2a above and will be approved by the US Army Depot Sys-

tems Command RPO.

7. Users of the CS-i, CS-12, and B-1093 check sources, the MX-7338/PDR-27( )

Radioactive Test Sample and Thorium NVD's do not require specific radiation pro-

tection training other than familiarization with the TMts for, or provided with,

the radiac instruments and/or components utilizing the radioactive materials.

The TMs provide users with specific instructions on the operation, safe han-


dling, and control of the radioactive items and satisfies the radiation

protection requirements of 10 CFR, Parts 19 and 20.


SUPPLEMENT F


2. Facilities for use of the AN/UDM-1 and/or -1A Radiac Calibrator Sets will be

approved by the CECOM Safety Office in conjunction with the requisitioning RPO

and will be designated Radiation Area or High Radiation Area as

determined/approved by the RPO. These areas will be equipped with control

devices or positive indicators which will energize a conspicuous audio or visual

alarm when the source is exposed and/or in its operating position. Access to

these and all radiation/

radioactive material areas will be restricted to authorized personnel. Tempo-

rary or permanent shielding such as lead bricks and sheets will be employed to

reduce unnecessary exposure when time and distance factors alone are inadequate.

In general, shielding will be used whenever feasible to minimize exposure to

personnel. Storage facilities for the AN/UDM-1 and -lA'Radiac Calibrator Sets

will be designated radiation or radioactive material area as determined/approved

by the RPO. In order to assure compliance to the above condition, health phy-

sics personnel from the CECOM Safety Office and/or qualified US Army Test,

Measurement and Diagnostic Equipment Support Group (TSG) personnel will perform

radiation protection program evaluations, at a minimum of 2 year intervals, in

order to evaluate the use/storage facilities associated with the AN/UDM-1 and -

1A Radiac. Calibrator Sets. Previous site visits to facilities utilizing these

calibrator sets have identified compliance to the above requirements.

3. Facilities for use and storage of the AN/UDM-2; -6; -7C and M3A1 Radiac

Calibrator/Radioactive Source Sets and Am-241 VEX Source will be in appropria-

tely designated radiation or radioactive material areas for these purposes as

Page 1 of 4 Supplement F

determined/approved by the RPO.

4. Radiac Calibrator Sets, AN/UDM-2; -6; and -7C, used by mobile Electronic/

Radiological calibration teams will be used and stored in specially designed

semi-truck trailers, access to which is limited to team members. At least one

team member will be qualified and approved as RPO having received a minimum of

40 hours training as indicated at paragraph 2a, Supplement E. The Radiac Cali-

brator Sets utilized by the calibration teams are stored in secure metal

cabinets/drawers within the calibration trailer and affixed with the appropriate

marking/posting requirements. The calibration trailers also contain calibrated

survey/monitoring equipment. Area surveys are performed on a monthly basis and

results documented. More generally, the surveys are performed prior to and

after each calibrator use.

5. Bulk storage, surveillance and issue of all calibrator/radioactive source

set assets, the MX-7338/PDR-27( ) Radioactive Test Sample and the CS-i, CS-12

and B-1093 check sources will be provided by LBAD, Lexington; KY and/or SAAD,

Sacramento, CA.

6. Bulk storage, surveillance and issue of the CS-I, CS-12 and B-1093 check

source assets, and the MX-7338/PDR-27( ) Radioactive Test samples incorporated

into End Article Applications (EAA), in addition to thermal system imaging

assets will be provided by Anniston Army Depot (ANAD), Anniston, AL; LBAD, KY;

Mainz Army Depot (MAAD), Mainz, GE; New Cumberland Army Depot (NCAD), New Cum-

berland, PA; Red River Army Depot (RRAD), Texarkana, TX; SAAD, Sacramento, CA;

and/or Sharpe Army Depot (SHAD), Lathrop, CA.


7. DA activities authorized to possess the radioactive materials indicated at

Supplement B, exclusive of the CS-i, CS-12 and B-1093 check sources and thermal

imaging system assets, are required to possess radiation detection/measure-

ment instrumentation such as the AN/PDR-56F and/or AN/PDR-60 Alpha Radiac Sets

and the AN/PDR-27( ) standard Army beta-gamma detection instrument, or commer-

cially equivalent instruments, as appropriate. Exception is made to the CS-i,

CS-12 and B-1093 check sources and thermal imaging devices due to the negligible

radiological hazard potential associated with these radioactive materials.

8. The AN/PDR-27( ) standard Army beta-gamma detection instrument and the

AN/PDR-56F and AN/PDR-60 Alpha Radiac Sets used for Active (Health and Safety)

purposes are calibrated IAW the procedures outlined in Technical Bulletin (TB)

9-6665-285-15, Army Calibration Program for Radiac Survey Meters; and

TB 750-25-i, Maintenance of Supplies and Equipment: Army Test, Measurement, and

Diagnostic Equipment (TMDE) Calibration and Repair Support Program. These pro-

cedures state that Active meters must be calibrated at two points on each scale

with each point separated by at least 50 percent of the maximum scale reading

and survey meter tolerance of each calibration point must be within + 10 percent

of the standards calculated values. Calibration standards used for the AN/PDR-

27() are the AN/UDM-I (Co-60), AN/UDM-iA (Cs-137) or equivalent, and are certi-

fied by, or traceable to, the National Bureau of Standards (NBS). The AN/UDM-6

and/or AN/UDM-7C Radiac Calibrator Sets are used for the calibration of the

AN/PDR-56F and/or AN/PDR-60 Alpha Radiac Sets. These calibrator sets utilize

Pu-239 and are traceable to the NBS. Frequency of calibration is as specified

in TB 43-180-i, Calibration and Repair Requirements for the Maintenance of Army

Materiel. Presently, the calibration frequency specified is once every 90 days.


,9. For personnel dosimetry, whole-body and wrist or ring beta-gamma film badge

or Thermoluminescent Dosimetry (TLD) service will be furnished by the US Army

Ionizing Radiation Dosimetry Center (AIRDC), Lexington, KY, IAW Army Regulation

(AR) 40-14, Control and Recording Procedures for Occupational Exposure to Ioniz-

ing Radiation and Supply Bulletin 11-206, Personnel Dosimetry Supply and Service

for Technical Ionizing Radiation Exposure Control (Enclosures 1 and 2). Film

badges and/or TLDs are processed monthly. Reports of exposure, as provided by

AIRDC, are transcribed by the custodian of the record onto DD Form 1141, Record

of Occupational Exposure to Ionizing Radiation. These records are maintained in

the users medical file and are available for review as required by AR 40-14.

Film badge, TLDs, and dosimeters will not be utilized for individuals using the

CS-I, CS-12 and B-1093 check sources; the MX-7338/PDR-27( ) Radioactive Test

Sample, the AN/UDM-6 and AN/UDM-7C Radiac Calibrator Sets and NVDs since it is

unlikely that these individuals would receive a dose in any calendar quarter in

excess of 5 percent of the applicable value specified in Title 10, CFR and AR

40-14.


SUPPLEMENT G


2. The Army program for control of radioactive items of supply is prescribed

specifically in two regulations. AR 700-64, Radioactive Commodities in the DOD

Supply Systems (Enclosure 1), is an interservice regulation which prescribes

responsibilities for control of radioactive items and components which are

introduced in the supply system. AR 385-11, Ionizing Radiation Protection

(Enclosure 2), establishes requirements for obtaining NRC licenses for radio-

active materials,, authorizations to possess radioactive material not controlled

by the NRC, requirements for individually controlled items of supply, transport-

ation of radioactive materials and the disposal of unwanted radioactive

material. Major Army commands and all Army activities are required to implement

these DA regulations as required/supplemented through appropriate command chan-

nels.

3. The authority contained in the NRC license/DA Radiation Authorization (DARA)

is'sued to CECOM permits DA installations and activities to acquire and use cer-

tain radioactive materials and items incorporating radioactive material without

obtaining their own license/DARA for these items. This is based upon commit-

ments made by CECOM that all Army elements will comply with conditions. contained

in those licenses and with pertinent Federal, DOD and Army regulations. Both

NRC and DA require control of all operations involving radioactive materials to

insure the safety of personnel and property. Army. activities possessing li-

censed radioactive sources and the agencies controlling them are subject to

inspection by the NRC in addition to inspection by Army elements.

Page 1 of 17 Supplement G

4. The mission of CECOM includes the management and performance of all material

life cycle functions and services and to act as DA licensee for Army-wide dis-

tribution of these items. The following describes the functions of the various

CECOM elements providing a coordinated effort:

a. The functions of manager for the NRC license/DARA are assigned to the

Chief, Safety Office of this-headquarters. The responsibilities of the manager

are as follows:

(1) Coordinate, obtain, administer, review, amend and maintain neces-

sary licenses/DARAs for radioactive commodities managed by this command.

(2) Provide information and guidance to all commanders with respect to

limitations, constraints, conditions or procedures which affect the responsibil-

ities of those commanders for the radioactive commodity.

(3) Monitor the life cycle program of the radioactive commodities to

assure compliance with conditions of the applicable license/DARA.

(4) Assure that licensed/authorized material is not transferred to

unauthorized persons or organizations.

b. CECOM health physicists serve as staff contact for radiation control and

NRC license/DARA related matters to the Army Materiel Command (AMC), other major

commands, DA elements, other services and federal agencies. They provide advice

and assistance to depots, Army elements and other CECOM elements involved in the

fielding of radioactive items, i.e., the National Inventory Control Point

(NICP). In addition, the CECOM health physics staff prepare radiation safety

instructions for incorporation in technical literature and other published gui-


dance pertaining to the items; coordinate with the NICP to assure that

requisitioning elements are authorized to and technically capable of receiving

the item and the procurements do not exceed the quantity or use limitations

imposed by the license/DARA; perform pre-award and post award health physics

surveys of contractors facilities; provide health physics advice to include

instructions for disposal of radioactive waste, and serve as staff officers for

notification, investigation, and preparation of reports required in the event of

an accident or incident involving radioactive items managed by this command.

c. The CECOM NICP in conjunction with the CECOM Safety Office, has adopted

special procedures for individually controlled radioactive items that are in

.,_:-addition to standard Army supply practices used for all type classified items.

These controls include insuring that the 'item is coded in the Commodity Command

Standard System (CCSS) Automated Data Processing Program as "radioactive" IAW

Appendix A of AR 708-1, Cataloging and Supply Management Data. The item is

coded with a Special Control Item Code (SCIC) indicating it contains radioactive

material. Requisitions are processed initially by computers and due to the

radioactive SCIC designation, are then processed manually by the NICP to verify

that the requisitioners are authorized to receive the item. The item manager

also provides the user/shipper with appropriate regulatory information, i.e.,

radioactive material exception data, related to the receipt, possession, move-

ment and disposal of the materials. The CCSS supports the AMC material

readiness function by providing comprehensive logistical management data for

items contained within the Army Supply System. Information inputed into the

CCSS is transmitted for incorporation into the Army Master Data File (AMDF).

The AMDF is disseminated worldwide to effected Army elements in order to provide

information necessary for proper management/handling of the item. Further con-


trol procedures include maintenance of a computerized data retrieval system that

contains information such as the radioactive commodity type number, serial

number, location, responsible RPO, alternate RPO, if applicable, their qualifi-

cations, and all leak test results. This information is reviewed by CECOM

health physics personnel on a monthly basis for accuracy, significant leak test

results and issuance of notices for required leak tests. In addition, the NICP

maintains records of procurements, receipts, storage locations, shipments, using

locations, and authorizes, issues, and assures adequate supply. Reports of

excess items are submitted through Army channels to the NICP for review of ser-

viceability, turn-in, or disposal as radioactive waste. Requisitions originated

by using elements are reviewed for radiation protection requirements and logis-

tics authority for possession. When approved, the requisition is forwarded to

the NICP which issues material release orders to the designated depot for ship-

ment of the material directly to the requisitioner.

d. The major Army commands have established regulatory requirements for

control of the radioactive items. As provided for by AR 385-11, each major com-

mand has established at the headquarters level, a radioactive material control

point and appointed a command RCO to administer control of radioactive items

within the major commands. The RCO reviews and concurs.in the qualifications of

local RPOs within the major command, maintains records of radioactive items by

location, assures periodic inventory and leak tests by using activities, per-

forms periodic inspection/audits of accountable installations/activities to

assure that the items are properly handled IAW Army and NRC regulations, and

assures the submission of inventory, leak test, and/or accident/incident reports

to the appropriate commodity command as required by Army regulations. The RPO

is responsible for administering the local radiation protection program. Local


Programs provide for designated controlled areas, dosimetry, instrumentation,

operating procedures to supplement published manuals for the items, receipts,

transfers, storage and records.

e. CECOM is designated Primary Inventory Control Activity (PICA) for Feder-

al Supply Classification (FSC) 5855 commodities which includes Night Vision

equipment. For FSC 5855 thermal imaging systems used as ancillary subsystems to

fire control systems managed by other commands, CECOM only maintains PICA re-

sponsibilities for the thermal imaging subsystems (common modules) whereas the

primary armament subsystem manager maintains full PICA responsibility for the

fire control system and all ancillary subsystems including thermal imaging sys-

tems, but excluding the thermal imaging subsystems. In this regard, CEQOM has

.been delegated the responsibility of maintaining overall license/regulatory con-

trol over the thermal imaging systems/subsystems within the Army Supply System.

This control is implemented by effected Memorandums of Understanding

(MOU)/Support Agreements between this command and the other AMC Major Subordi-

nate Commands (MSC) who are designated as the weapon systems managers for the

applicable EAA. Delegation. of responsibilities regarding these MOU/Support

Agreements includes the following provisions:

(1) CECOM will:

(a) Perform all duties as indicated in this radiation protection pro-

gram.

(b) Maintain the required NRC license.

(c) Coordinate with AMC MSC's prior to amending the NRC license for

changes which may affect their mission function.


(d) Assure that all radioactive components are coded with the appro-

priate SCIC to indicate that the item utilizes/contains radioactive material.

(2) Effected AMC MSC's will:

(a) Insure that the thermal imaging systems and subsystems assigned to

them are coded with an SCIC indicating the item incorporates radioactive mater-

ial.

(b) Insure that an annual report of the total number of thermal

imaging systems/subsystems/component asset posture, depot asset posture,. the

total number of procured systems/subsystems/components by contract number, and

identification of future procurements of systems/subsystems/components are fur-

nished to the CECOM Safety Office.

(c) Insure that all radioactive items assigned to them are disposed of

as radioactive waste and provide the CECOM Safety Office with an annual notific-

ation of the total number disposed.

(d) Insure that the technical literature contains the required

radiation warnings/statements, and that proposed changes to these warnings/

statements are coordinated with the CECOM Safety Office.

(e) Inspect depots on an annual basis that are not evaluated by CECOM

in order to determine compliance with the authorizing NRC license/DARA. This

shall include annual QA inspections of thermal imaging systems and subsystems

under their purview.

(f) Insure that all optical elements and lens coatings of thermal

imaging systems and subsystems are in compliance with 10.CFR and with NRC

Page 6 of. 17 Supplement G

license requirements.

f. For bulk storage of radioactive materials, the depots have established

warehousing facilities and handling procedures governed by a formal radiation

protection program end administered by',ualified RPO s. The storage installa-

tionz. (warehoUle) are generally o. cinder block and brick construction with

as.halt covered wooden roof. The instellations are protected by fire sprinkler

systems and/or supporting fire den"rtments. All buildings are locked when not

ccpi e d and the installation. (depot.) perimeters are secured by fence and employ

roving patrols and sentries at the gate(s). CECCM health physics personnel

annually review the programs to ensure compliance to the requirements in the

governing NC license/DATA and s..pportng documentation. Padicactive items are

.nsnected when received, at intervals during storage and prior to shipment.

Item i-snections are conducted according to established surveillance procedures

as deterr--.ned by CZCOM.

g. Maintenance and quality surveillanc of the AN/UDM-1; -A; -2; -6; -7C

and M3AI Fadiac Cal.brator/rad 0a2Ctve Source Sets wi be ro,,vi ied by LBAD

and/or SAAD. Pec=l-_bration and analysis of leak tests for the AN/UDM-,; -!A, -

2; -6; -7C and M3'A",'A ,adiac Calibrator/Radioactive Source Sets will be performed

by oualifed personnel of the Area Calibration and Pepair Center (ACRC) -

LBAD/ATRDC, Lexington, KY; the Nucleonics Laboratory Branch, ACRC - Sacramento,

SAAD, Sacramento, CA; the 2nd Maintenance Company, Camp Carroll, Korea; and/or

the 52tth Maintenance Comnany', Pirmasens, Germany. Infornation provided at

Table G-. identifies current recalibration frequencies and-locations, in addi-

tion to leak testing intervals.., Al!celibrator sets are eva-luated for leakage

of radioactive matera 1 prior to shipment. Leak test anaJ.ýsis will also be pro-

page 7 of 17 SUPn"7meft G "

' 1i-

vided by AIRDC, Lexington, KY. Health physics laboratory counting equipment a~t

the above locations are capable of measuring 0.001 uCi of removeable contamin-

ation. No maintenance will be performed on the radioactive material/radiation

source utilized in these Radiac Calibrator Sets. Excluding the AN/UDM-1 and -1A

Radiac Calibrator Sets, necessary maintenance that might be performed is the

removal/exchange of sealed sources and minor repairs of the storage cases.

Removal/exchange of sealed sources contained in the AN/UDM-1 and -1A will be

provided by the manufacturer.

h. ANAD, MAAD and/or SAAD, will provide maintenance and serviceability for

thermal imaging systems limited to the necessary removal/exchange of ThF 4 coated

optics. There will be no maintenance and/or serviceability performed which

involves the grinding or removal of the ThF4 coatings from these equipments.

Maintenance of this nature will be provided by an approved contractor.

(1) No maintenance will be performed involving the radioactive compo-

nent of the CS-i, CS-12, and B-1093 check sources the MX-7338/PDR-

27( ) Radioactive Test Sample and the Am-241 VEX Source.

i. QA/Quality Surveillance for the AN/UDM-1; -1A; -2; -6; and -7C and M3A1

Radiac Calibrator/Radioactive Source Set:

(1) Future refurbishments:

(a) First Article Testing (FAT) of the sources incorporated within the

above calibrator/source sets will be witnessed by CECOM Safety Office health

physics personnel or qualified designees in order to assure compliance with

applicable military specifications, drawing specifications and any

amendments/revisions thereto.


(b) Government witnessing of the contractor providing the sources will

be performed by CECOM Safety Office health physics personnel or qualified desig-

nees in order to assure compliance with. DOT and IAEA Special Form testing

requirements and/or ANSI sealed source classification testing requirements,

where appropriate.

(c) Government verification of the contract requirements as stipulated

in the applicable military specification/drawing specifications, and any amend-

ments/revisions thereto, will be performed by representative from the Defense

Contract Administrative Services (DCAS).

(d) Independent QA inspection of the sources will be performed by

either CECOM Safety Office health physics personnel, LBAD and/or SAAD RPO or a

qualified designee, the AIRDC RPO/health physics representatives or the Belvoir

Research and Development Center's (BRDC) Material Technology Laboratory RPO/

health physics representatives. QA procedures will involve leak testing of the

radioactive sources/components. Standard non-radiological QA inspection of the

assembled calibrator/source sets will be performed by LBAD/SAAD supply repre-

sentatives. Verification of the radiation output (calibration check) will be

performed by the ACRC-LBAD and/or ACRC-SAAD prior to fielding. ACRC-SAAD will

also perform additional leak testing requirements prior to fielding. There will

be no source failure regarding leak testing requirements. The contractor will

be responsible for correcting all defects pertaining to the sources. The entire

calibrator/source set or the effected component(s) will be returned to the con-

tractor for correction of the defect.


(2) New procurements:

(a) FAT, DOT/IAEA Special Form, ANSI sealed source classification.

testing, DCAS verification and independent QA inspection, where appropriate,

will be performed as indicated in subparagraph (1)(a) through (1)(d) above.

(b) There will be no source failure of leak testing requirements.

(c) The contractor will be responsible for correcting defects regarding

the calibrator/source sets. All calibrator/source sets will be returned to the

contractor for this purpose.

(3) Quality surveillance program will be performed by the

their designated alternates or by CECOM health physics personnel.

clude the annual leak testing of a random sampling of at least one

depot assets and/or a minimum of. five each, whichever is greater.

will provide results to: Commander, USACECOM, ATTN: AMSEL-SF-MR,

mouth, NJ 07703-5024.

depot RPO's,

This will in-

percent of

The depot

Fort Mon-

j. QA/Quality Surveillance of the MX-7338/PDR-27( ) Radioactive Test

Sample.

(1) New Procurements:

(a) FAT of the MX-7338/PDR-27( ) Radioactive Test Samples will be wit-

nessed by CECOM Safety Office health physics personnel to assure compliance with

MIL-R-51305(MU) and any amendments/revisions thereto.

(b) Government verification of the contract requirements as stipulated

in MIL-R-51305(MU), and any amendment/revisions thereto, will be performed by a


representative from the DCAS.

(c) Independent government testing of the FAT sealed sources will be

performed by qualified representatives from the US Army Armament, Munitions and

Chemical Command (AMCCOM), Aberdeen Proving Ground, MD; AIRDC; BRDC and/or

CECOM.

(d) Independent QA inspection of the sealed sources will be performed

by CECOM, qualified representative from BRDC, AIRDC and/or AMCCOM. QA proce-

dures will involve the random sampling of MX-7338/PDR-27( ) Radioactive Test

Samples IAW Military Standard (MIL-STD)105D, Sampling Procedures and Tables for

Inspection by Attributes, and appropriate testing requirements as indicated in

MIL-R-51305(MU).

(2) Quality surveillance will be performed annually by the RPO, their

alternates, or CECOM health physics personnel. The radioactive test samples

shall be inspected and/or tested as indicated in paragraphs (a) through (c)

below. Test results shall be within the stipulated Acceptable Quality Level

(AQL) as stipulated in MIL-STD-105D.

(a) Activity: Using a calibrated AN/PDR-27( ) Radiac Set at the 50

mR/hr range, test each radioactive test sample by placing the active (colored)

end in direct parallel contact with the center portion of the high range (smal-

ler) probe. The meter reading should be at least 10 mR/hr. If the reading is

less than 10 mR/hr, the radioactive test sample is considered unserviceable and,

along with the identification tag, is to be disposed of as radioactive waste IAW

AR 385-11 (AQL is 1.5 percent).


(b) Visual Inspection of the Identification Tag Attached to the

Radioactive Test Sample. If the identification tag is missing and/or illegible,

the radioactive test sample is considered unserviceable and is to be disposed of

as radioactive waste IAW AR 385-11.

(c) Visual Inspection of the Radioactive Test Sample. Determine if the

test sample is crushed, damaged or deformed. If visual inspection indicates

damage, the radioactive test sample and the identification tag are to be dispo-

sed of as radioactive waste IAW AR 385-11.

k. QA/Quality Surveillance for Thorium Fluoride Coated Optics:

(1) Future refurbishments/new procurements: Testing is inclusive of

the following, or equivalent, and will be verified by a representative from

DCAS:

(a) A witness sample from each coating run shall be subjected to the

hardness and adherence tests as specified in paragraphs 4.4.5 and 4.4.6 of MIL-

M-13508C, Mirror, Front Surfaced Aluminized: For Optical Elements.

(b) A witness sample from each coating run shall be subjected to the 10

day humidity test of Method 507.1 of MIL-STD-810, Environmental Test Methods.

(c) A witness sample from each coating run shall be subjected to the

salt spray (fog) test as specified in paragraph 4.6.10 of MIL-C-675, Coating of

Glass Optical Elements (Anti-Reflective).

In addition, the durability of all IR coatings shall be tested to

insure that a sample from every batch of coated optical elements meets or

exceeds the scotch tape, eraser rub and environmental tests as specified in the


following Mli tary Snecifications and/or Standards: MIL-C-675, MIL-M-!3508rv

Y!L-STD-810 and M7 C-4040", Coating, Single or Multilayer, Interference: Dura-

bility •-•uirements For.

There will no be marking requirements for these devices based upon

the revision made to Section L'C.22, 10 CFR Part 40. Further, in the NRC's Sta-

tements of Consideration (40-SC-10) concerning this revision, it was pointed out

that paragraph (a)(4) of Section '40.22 is applicable to any size unit, other

than individuals, which is physically separate from other units.

(2) Quality surveillance procedures for thermal imaging systems will

_nvowve " the anrnal visual inspection of a random samoling of at least six each

F-11 assets and/or at least one percent of depot Fssets, whichever is greater,

for flaking and/or pitting of the ThF. coatfngs. FLIRs may be developed as

,ne replaceable ts .. S), prepackaged portions of imaging systems to

faciltate feld replacement. •These items may not readily lend themselves to

ality assurance testing of the coatings of the individual lenses involved. In

such cases quality assurance/surveillance will be performed on lens coatings

during maintenance to assure that unsatisfactory coatings do not exist in the

field. Degradation of coatings will produce a comparable reduction in operatio-

ral capabilities thus significant difficulties with coating quality of fielded

items Would be idert,- .

I. QA/Quality Surveillance for the CS-,. CS-12 and B-1093 Check Sources:

(1) New procurements: Exclusive of the B-10093, there wil be no new

procurements of check sources.


(2) Quality surveillance: Quality surveillance of the CS-1 and CS-12

check sources will- involve annual adherence testing of "he sources active area

for at least one percent of depot assets a.d/or a ininmum of five each, which-

ever is greater. Due to the physical design of the B-1,cl`) check source, no

qva.ity surv&'½nce of this check source Js necessary. However, adherence of

the check source to the underside of the AN/PDR-56F Radiac Set will be verified

for at least one percent of deDot assets and/or a minimum of five each, which-

ever is greater.

m. Regulatory guidance for control of the radioactive materials/commodities

indicated at Supolement B has been established by DA governing the management

process, possession nnd use of radioactive materials, to include specific

reporting -.rocedures for incidences voiving loss, theft and misuse, control of

personnel radiation exposure, safe storage, handling, maintenance, transport-

ation and disposal of the items. Controls include ½suring that the radioactive

item/commodity is coded with a SCIC indicating its radioactive content. Addi-

tional controls include:

(!) Monthly printouts:ccntaining all known radioactive commodities,Na- 2. or a S -ock ef

_N!tj.ora' Stock Numbers ( iSN), 'tem manager codes, and demi!itarization

codes are orov4 ded the CECOV health physics staff. This information is revised

when new radi oacti've items are discovered.

(2) Monthly printouts indicating planned changes to be made in the

SC-Cs assigned to radioactive commodities as well as the individual responsible

for making them. These changes are held in the CCSS for 60 days prior to actu-

ally implementing the changes. In this manner, tracking of all planned changes

in the system can be accomnlished prior to actua! changes thereby preventing the'q , • ' -4 -'


loss of control over radioactive commodities.

(3) Procurement Work Directive printouts are Drovided to CECOM health

physicists for all planned procurements of radioactive commodities for approval

or disapproval. Additional printouts provide advance notice to all manual or

automated procurements of radioactive commodities.

(4) Th Directorate of International Logistics (IL), CECOM, coordinates

with CECOM health physics personnel, on foreign military sale (FMS) cases for

all radioactive commodity components and EAAs incorporating these components.

IL is required to notify all FMS customers of all radioactive components, by

radionucli de and activity, of EAAs offered for purchase so as to preclude sale

of radioativýe material to foreign countries not wishing to receive it.. Fur-

ther, CECOM health physics personnel, upon request, provide IL with advanced

exception data advisig the receiving country to contact their radiation protec-

tion organization for appropriate guidance. This advance notice of FMS cases

allows C ECOV:_eh physicists to review applicable rules of export for specific

;,adiaactiý,ve mat er;Jisal govern 6d r4

n. Presently, the irl-lementation of a Hazardous Materiel Data System (HMDS)

is. utilized in conjunction with normal •-o-i-t"ca handling. The H.0 is a com-

puterized system providing Army elements with reo.vired shipping information.

The following informat•on is, generally common to all listed NSNs coded with an

SCIC indicating radioactive content: i t em Nomenclature, Maximum Activity,

Radionuclide, Chemical/Plhysical Form, Prinary Tnventory Control Activity, Tran-

spo-rt' Index, Fissi-e C ls, license or DA Authorization Number and Special

Thstruction Narrative.

Page 15 of 17 Supplement G./ 4

L/f

0. U'sers of the Padiac Calibator Sets are provided with specific instruc-

tions on safe handling, storage ahd transportation as described in the TB's/TM's

proviced. with each calibrator set. Radiation yarning/caution statements are

Placed within the T7/T . for !AA's contai n½g radiactive materials. In addi-

tion, Form YnC-3, totie to Employees, and Section 206 of the Energy

Sei.reanization Act of 1974, arc provided within the aforementioned technical

literature. Commander, UJACECOM, ATTN: AMSEL-SF-MP, Fort Monrrouth, New Jersey

"773••n02=4 will make available, upon request, to the major commands and users,

the appropriate NRC regulations, the NRC license, license conditions, documents

incorporated into the license by reference, and amendments thereto, and any

noýice of violation involving radio~oica! working conditions for examination.

T. In ev uating p~ssi e ra~if o'olo i -a' hazard resultant from ut ization of

the radioactive materials i:':dicated at Supplement B, Environmertal Assessments

(EAl were pr-pared based on conservative assumotions which lcad to the conclu-

ciont hath e internal/externa! exposure rate would not exceed regulatory limits

stipulated for occupational workers. Exposure levels presented confirm the fact

that utilization of the rai oactive material. indicated at Supplement B posesinsignificant to non-existent radiologiea!/environental hazard. The EAs are

p)rovided re eie at Annex 7. 7or those 7A's that have previously been pro-

vided for s 4,C licensing requests, an addeundum to the -A is included to

reflect current CECOM policy regarding the radioactive com.modity.


TABLE G-1

Leak Test/Recalibration Frequency

Commodity

AN/UDM- 1

AN/UDM-1A

AN/UDM-2

AN/UDM-6

AN/UDM-7 C

M3A1

Am-241 VEX

Leak TestInterval

6 months

6 months

6 months

3 months

3 months

6 months

6 months

WhereDone

on-site

on-site

on-site

on-site

on-site

on-site

RecalibrationInterval

annually

every 2 years

every 2 years

every 2 years

annually

annually

WhereDone

on-site

on-site

calibration lab

calibration lab

calibration lab

on-site orcalibration lab

on-site orcalibration lab

on-site N/A


SUPPLEMENT H


2. Disposal of the radioactive materials indicated at Supplement B may be

accomplished by return to the appropriate manufacturer, as applicable, and/or

through established DA channels lAW 10 CFR, AR 385-11 and AR 700-64. Initial

requests for disposition are submitted to Headquarters, CECOM for review. After

determination has been made for final disposition as radioactive waste, CECOM

authorizes the user to dispose of the radioactive material in accordance with AR

385-11. Headquarters, AMCCOM has been delegated the responsibility of manage-

ment coordination for radioactive waste disposal. AMCCOM assures that all

radioactive wastes are packaged and shipped in accordance with all applicable

requirements for ultimate transfer of the radioactive waste to an authorized

burial site. Requests for disposal of transuranic elements are provided to the

US Department of Energy (DOE) through AMCCOM. The DOE provides disposition

instructions, inclusive of compliance requirements to DOT regulations, for ship-

ment to specified DOE installations for ultimate disposal of the material as

radioactive waste.

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