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9 g .______a- -_____ -mm - - mmm.. ------...m... 9 NRC FORM 374 1 2 ~ 't (10-89) U.S. NUCLE AR REGULATORY COMMISSION '^"AmendmenENo.04 't i MATERIALS LICENSE Ig !E Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, !g ; Code of Federal Regulations. Chapter 1. Parts 30,31. 32,33,34,35, 39,40 and 70, and in reliance on statements and representations heretofore p made by the licensee, a license is hereby issued authorizing the licensee to receive. acquire, possess, and transfer byproduct, source. and special . ;N nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated below; to deliver or transfer such material |I to persons authorized to receive it in accordance with the regulations of the applicable Partf s). This hcense shall be deemed to contain the conditions

specified in section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations and orders of the Nuclear |

, Regulatory Commission now or hereafter in effect and to any conditions specified below. !g!

n ' ' * " ' * * In accordance with application dated July 23,1992 !N! ; l- Department of the Army 3. Ucense number SUC-1391 is amended in f I its entirety to read as follows: |g i ' ' , ! i - Tooele Army Depot | 4. Expiration date March 31,'1998 || - - Tooele, Utah 84074-5008 :gi 5. Docket or ig| j . Reference No 040-08779 ; f, 6. Byproduct, source. and/or 7. Chemical and/or physical 8. Maximum amount that hcensee i special nuclear material form may possess at any one time under this license

; Uranium (Depleted in A. Depleted uranium A.3,500,000 kilograms j 1A.uranium-235) alloy component i installed in military ammunition i Uranium (Depleted in B. Shielding material B. 200 kilograms uranium-235) ! : |B. ; g 9. Authorized use: " q A. For handling, storage, and demilitarization of munitions containing depleted j q uranium; storage of bulk depleted uranium; and shielding in radiographic i H exposure devices. | 4 B. f | For use as shielding in a Varian Linetron 200 linear accelerator. j f CONDITIONS - i ,, g 10. A. Licensed material specified in Item 6.A. shall be used only at Tooele Army 1 R Depot, Tooele, Utah. |B I . | B. Licensed material specified in Item 6.B. shall be used at the Pueblo Depot {H q Activity, Pueblo, Colorado. |g , I bi ! 11. Licensed material shall be used by, or under the supervision of, Bryce R. f g Christensen or Harold K. Oliver. p

4 . > I 9306070281 930316 | | PDR ADOCK 04008779 g g C PDR y

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ym m im mmmm mmm m mm m ------m m m mmmm m mmmmm m m = - .; 4 Nec Form 374A . U.S. NUCLEAR REGULATORV COMMISSION PAGE 2 OF 2 PAGES fI 4 0 84) License number !E SUC-1391 MATERIALS LICENSE " ' * ' * " " " " * i SUPPLEMENTARY SHEET jf 040-08779 .p 3 A F 1 Amendment No.-04 W W 4 l'Eb 'N 4 I E 1 4 F 9 ( 12. Except as specifically provided otherwise in this license, the licensee shall 3 4 conduct its program in accordance with the statements, representations, and iN 4 procedures contained in the documents, including any enclosures, listed below. .The i !' Nuclear Regulatory Commission's regulations shall govern unless the statements, j | representations, and procedures in the licensee's application and correspondence are !,| 4 - q more restrictive than the regulations. A . |f- A. Application dated July 23, 1992 jP (W h 4 |H 4 h 4 E 4 P 4 ii> 4 '!E Q in C n A g i@g. - 4 5 A > ;Y d . ' Q $ d !P 4 .!d ;G 'D 4 |p - a | Q j g , d , d ! 1 j . :1 j d ; d :i 4 a #e :s |> it )1 $ ' 4 |F 4 FOR THE U.S. NUCLEAR REGULATORY COMMISSION + h |E 4 |1 4 Original Signed By |1 t&R I 6 1993 william L Fisher ;j |Date By gj Nuclear Materials Licensing Section Il 4 Region IV |P) 4 Arlington, Texas 76011 |P: 4 ,h; 4 'h: !; ! 4 ( . !>P; 'd R i .a!f

. _ , ,. C..u-_ -.. _ _.-____----_ UNITED STATES y_ a alGug?_ g. NUCLEAR REGULATORY COMMISSION Y REGION IV 611 RY AN PLAZA DRIVE, SulTE 400 o, 8 <, 8 ARLINGTON, TEXAS 760118064 ..... MAR I 61993 -

Department of the Army ATTN: Bryce R. Christensen Tooele Army Depot Tooele, Utah 84074-5008

Gentlemen:

Please find enclosed Amendment No. 04 renewing your NRC material license. You should review this amendment carefully and be sure that you understand all conditions. If you have any questions, you may contact the reviewer who signed your license amendment at 817/860-8100. Please be advised that you must conduct your program involving radioactive materials in accordance with the conditions of your NRC license, representations made in your license application, and NRC regulations. In particular, note that you must:

1. Operate in accordance with NRC regulations 10 CFR Part 19, " Notices, Instructions and Reports to Workers: Inspection and Investigations," 10 CFR Part 20, " Standards for Protection Against Radiation," and other applicable regulations.

2. Possess radioactive material only in the quantity and form indicated in your license.

3. Use radioactive material only for the purpose (s) indicated in your license.

4. Notify NRC in writing of any change in mailing address (no fee required if the location of radioactive material remains the same).

5. Request and obtain written NRC consent before transferring your license- or any right thereunder, either voluntarily or involuntarily, directly or indirectly, through transfer of control of your license to any person or entity. A transfer of control of your license includes not only _a total change of ownership, but also a change in the controlling interest in your company whether it is a corporation, partnership, or other entity. In addition, appropriate license amendments must be requested ! and obtained for any other planned changes'in your facility or program that'are contrary to your license or contrary to representations made in your license application, as well as supplemental correspondence thereto, which are incorporated into your license. A license fee may be charged for the amendments if you are not in a fee-exempt category.

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; 6. Submit a complete ' renewal. application with proper. fee, or termination- t request at least 30 days before the expiration date-on your license. You will receive a reminder notice approximately 90 days before the expiration date. Possession of radioactive material after your license

expires is a violation.of NRC regulations. ;

7. Request termination of your license if you plan to permanently i' discontinue activities involving radioactive material. You will be periodically inspected by NRC. A fee may be charged for inspections in accordance with 10 CFR Part 170. Failure to conduct your

program in accordance with NRC regulations, license conditions, and , representations.made in your license application and- supplemental ' correspondence with NRC will result in enforcement action-against you. This could include issuance of a noti.e of violation; imposition of a civil ' penalty; or an order suspending, modifying, or revoking your license as

, specified in the General Policy and Procedures for_ NRC Enforcement Action,10 ' CFR Part 2, Appendix C. Since serious consequences to employees and the. public can result from failure to comply with NRC requirements, prompt and vigorous enforcement action will be taken when dealing with licensees who= do not achieve the necessary meticulous attention to detail and the high standard = ' of compliance which the NRC expects of its licensees. Thank you for your cooperation.

Sincerely, i

Original Signed By | William L Fisher ! Robert A.-Brown Nuclear Materials Licensing Section j Enclosure: As stated

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( >. - $p.f4tGu UNITED STATES + NUCLEAR REGULATORY COMMISSION , _ $g , N o REGION IV % < o, 611 RYAN PLAZA DRIVE, SUITE 400 v, e[ AR LINGTON, TEXAS 76011-8064 ***** AUG 5 1992

Department of the Army Docket No. 040-08779 ATTN: Gail Christiansen License No. SUC-1391 Tooele Army Depot Control No. 464344 Tooele, Utah 84074 i

Gentlemen:

This is to acknowledge receipt of your application for renewal of the special , nuclear materials license identified above. Your application is' deemed timely filed and, accordingly, the license will not expire until final rction has been taken by this office. Any correspondence regarding the renewal application should reference _ the control number specified and your license number. Sincerely,

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Billie Gruszynski (Ms.) Nuclear Materials Licensing Section

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; c.. j i ggy . DEPARTMENT OF THE ARMY

. 5001 EISENHOWER AVENUE, ALEXANDRIA, VA 22333 0001 _ , , , , . August 26, 1992 ~ IElIJ&ior-

/G 311992 ! |

U.S. Nuclear Regulatory Carrmission Region IV Nuclear Materials Licensing Section 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011 : Reference: Renewal of U.S. Nuclear Regulatory Ommission License SUC-1391, issued to Tooele Army Depot, 'Iboele, Utah

Gentimen: Enclosed is the renewal application for NRC license SUC-1391, issued to Tooele Anny Depot, Utah. The license will expire on August 31, 1992.

We recmocnd approval of the raluest.

Thank you for your assistance in this tratter. For further infornation, please contact Mr. John Manfre at (703) 274-9340.

Sincerely,

i M6 .I _ John E. Rankin Chief Safety Office

Enclosure

Copies Furnishes 3: 011%NDER DESCOM, Al*IN: AMSDS-IN-S Iboele Army Depot, ATTN: SDSTE-IR-S

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ATPLtCATiONS FOR D*$YRat WTION OF E SEMPT PAODUCTS PsLE APPL 4C ATTON8 WITM 17 vou ARE LOCATED IN U S NUCLE AP ME GUL Atom e COMMsL5l' N 8Li e=Dit sNDe ANA. lon A MsCMSG AN. M8NhE 60T A. MIEbOUme OHIO. On Ot vi& ION DS INDUST mt AL ANO ME DeC AL NvCLt. AR S AF E T V h uh5 WiECO*.ON. 5E ND APPLsC.ATiONE TO. We ASMINGTON. OC 295bb U 8 NUCL.E AR RE GULAT OR T COMMISSION RE GiON 88: jp^ ALL DTME R PgRSOsiS plLE APPUCAT60NS A5 FOLLOws. 8F YOU ARE M AT E At AL8 uCE N5 SNG SE CTiCW Qy i OCJ1tTED IN T99 #DO&E VE LT MOAD GLLN ELLYN. it 6013T C ONNE CTicuT DELAm APE Oisin6c1 Or COLUMeiA M AINE . M An v LAND. M ASS AC Mu&rTT E NEW M AMP $Mf AE. NEW JL A&f Y hE W TORK. PE NNE TLV ANI A. AMR ANSAS COLOR ADO lDA MD E AN&As Lovess4NA. MONT Aesa hE BR AEm A EMODE iSLAseg. On ygpMONT. SEND APPUC ATIONS 70; hen ME m sCO. honTM D AmOT A Da L AMOM A. &OUT N DARO T A. T E R A&. WT AM

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AMOUN T A t ; E e vt D &ECe' NUMBER

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l Application (NRC form 313) to Renew NRC Material License #SUC-1391 | | , Tooele Army. Depot, Utah I ITEM #5. RADIOACTIVE MATERIAL. ! a. Uranium U238, depleted of U235 ] b. Milled solid metal, military ammunition component j

c. 3,500,000 kilograms maximum

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Application (NRC form 313) to Renew NRC Material License #SUC-1391'

Tooele Army Depot, Utah '

ITEM #6. PURPOSES FOR WHICH LICENSED MATERIAL WILL BE USED. The following DU munitions may be handled at TEAD: 1. Cartridge, 20mm,-US Navy, MK149, NRC #45-16023-01NA. ii. Cartridge, 25mm, PGU-20/U, US Navy, NRC #45-16023-01NA. iii. Cartridge, 25mm, M919, US Army, NRC /SUC-1380'. iv. Cartridge, 30mm, GAU-8, US Army, NRC /SUC-1394. v. Cartridge, 105mm,.M774/833/900, US Army, NRC #SUC-1380. vi. Cartridge, 120mm, M827/829, US Army,-NRC #SUC-1380. vii. Cartridge, 7.62mm, model not available, NRC #SUC-834. viii. Cartridge, .50 cal, model not available, NRC #SUC-834. iv. Pursuit Deterrent Munitions (PDM), mine, M86. x. Area Denial Artillery Munitions (ADAM),155mm, M692/M731.

a. Transportation, receipt & shipment, of individual containers and pallets of DU munitions.

b. Inspection of DU munitions during receipt, . storage and transportation activities. These inspections determine serviceability and may' include swipe tests of the sabot exterior for leakage of the DU from intact rounds. See supplement.2 for swipe test procedures.

c. Storage of DU munitions in earth-covered- magazines. Munitions will be stored in palletized transportation containers. The demilitaritized penetrators will be stored in strong, tight, containers. See Supplement 3 for radiation measurements of.the various munitions in storage.

d. Demilitarization of DU munitions. The DU will be separated from the explosive component. The DU may.be stored at TEAD or may be transferred to a NRC or Agreement State licensee 'who is authorized to receive it. Any sale of DU will be arranged by AMCCOM at Rock Island Illinois. At the present time, the Army is demiling only the 20mm and 30mm rounds as only these two rounds are separable. See Supplement 1 for a study on the demilitarization of Depleted Uranium Devices.

e. Evaluation and testing of demilitarization methods- for munitions. See supplement 4 for description of ADAM & PDM mine demil procedure development.

f. The DU controlled by this license will NOT be fired.

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Application (NRC form 313) to Renew NRC Material License #SUC-1391

Tooele-Army-Depot, Utah

ITEM #7. INDIVIDUALS RESPONSIBLE FOR RADIATION' SAFETY PROGRAM. a. Bryce R.-Christensen, TEAD Radiation Protection Officer Bachelor of Science, Business Administration,_ University _of - '

Phoenix, Salt Lake City, UT _ Army Radiological Safety (3 weeks) , Fort McClellan, Alabama, September 1991. Radioactive Waste Disposal (1 week),LChemical Nuclear- Corporation, Barnwell, South Carolina, June 1991.

Depleted Uranium Munitions Radiological Safety (1 week), Fort Belvoir, Virginia, May 1992.

Health Physics Instrumentation and Air Sampling for Radioactive Material (1 week), Fort Belvoir, Virginia, July 1992 Management of Radiological Accidents and Emergency Preparedness Training (1 week), Fort Belvoir, Virginia, *

August 1992. i TEAD RPO, since 1 January 1992, have handled H3, Ra226, Am241, Ca252, Cs137, Ni63, Co60, Pm147, Th232, Rn222'& Kr85.

Department of Army Civilian, Safety & Occupational Health Specialist, 3 years

b. Harold K. Oliver, TEAD Alternate Radiation Protection Officer

, Bachelor of Science, Mechanical Engineering, Utah State University, Logan, UT

Master of Engineering (Safety), Texas A&M University, Texarkana, TX Basic Radiological Health #211 (2 weeks), US Public Health- Service, Rockville, MD

Occupational Radiation Protection #212 (2 weeks), US Public i Health Service, Rockville, MD l

Department of Army Civilian, Supervisory Safety. Engineer,.22 j

years ;

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Tooele Army Depot ; ITEM #8. TRAINING FOR INDIVIDUALS WORKING IN OR FREQUENTING RESTRICTED AREAS. I. Training Outline:

a. Types & units of radiation. I

c. Biological effects of radiation.

d. ALARA: exposure limits, protective measures, dosimetry,- surveys & inspections, medical surveillance, personal' hygiene, protective clothing and restrictive signage.

e. Regulatory requirements: 1. NRC reg guides 7.1, 7.3, 8.10, 8.13, 8.29. ii. 10 CFR (NRC) parts 19, 20, 21, 40, 71. iii. Army regs 385-11 & 40-14. ' iv. NRC licenses issued-to TEAD. v. TEAD reg 385-11-(TEAD Radiation Program). vi. 49 CFR (DOT) subchapter C.

f. Depleted uranium specifics.

g. Standing Operating Procedures for work being-performedi- i II. Training Duration and Frequency.

a. Initial training (as outlined above) will last approximately three hours.

b. Annual training on the same topics will last one' hour,

c. Training records will be kept ~ by the RPO in the Safety Office,

d. Formal training (as outlined above) will be provided by'the

RPO or his designate. On-the-job training.and SOP familiarization , will be the responsibility of the supervisor of the operation.

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Application (NRC form 313) to Renew Materials License #SUC-1391

Tooele Army Depot, Utah ITEM #9: FACILITIES & EQUIPMENT.

a. Storage: Munitions containing DU will be stored in earth-covered magazines which are designed for ammunition storage. The number of munitions allowed in each will be determined by explosive weight in accordance to Army ' Regulation. 385-100 (Explosive Safety Manual) . Magazines designated for-DU. storage will be dedicated to DU and DU munitions. All magazines are kept locked except during authorized operations. The keys are kept under strict control. Required warning signs will be posted. DU may be stored in strong tight containers within an operations building, temporarily, until transfer to permanent storage in earth-covered magazines.

b. Demilitarization: Demil activities will be accomplished in Ammo Operations building #1375. Any non-radioactive component such as wind-screen will be removed when ever practicable to reduce the volume of radioactive material. The pull-apart' of the projectile and cartridge will be accomplished within a shield that will contain ignition of the round.

c. Radiation Detection: A whole body thermoluminescent dosimeter will be worn by persons handling DU. A ring or wrist ~ TLD may also be worn when appropriate. TLDs are provided and read by the Army Ionizing Radiation Dosimetry Center in Lexington Kentucky. TEAD has six Ludlum, model 3, survey meters with probes to detect alpha, beta or gamma. Eight Victoreen 492 survey meters are available. All survey meters are calibrated, in.90-day' cycles, by TMDE in Sacramento California or Ogden Utah. TMDE provides an emergency RPO kit consisting of an Eberline PRM-5 with probes for alpha, beta & gamma (The kit is exchanged _for a newly calibrated kit every 90 days.) TEAD has a Beckman LS100C liquid scintillation counter. TEAD currently has a gas proportional counter from Nuclear Measurement Corporation (PC-4) which will be replaced, by November 1992, with a new Tennelec/ Oxford LW5100 gas proportional counter. Several high volume and low volume pumps are available for air sampling use if there is a possibility that any DU may become airborne.

d. Air-borne alpha particles are not expected because the DU components are not being worked. Ventilation equipment will be used if air sampling determines a need. Fire or explosion are the only scenarios under which dust particles may be expected to be produced.

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Application (NRC form 313) to Renew Materials License #SUC-1391

Tooele-Army Depot,' Utah

. ITEM #11: WASTE MANAGEMENT. a. Unwanted radioactive material will be disposed of in. , accordance with AMCCOM Pamphlet 385-1 (Handbook for Disposal of ;

Unwanted Radioactive Material). The US Army Armament, Munitions & , Chemical Command (AMCCOM) has been designated as'the responsible ' agency for the safe disposal of radioactive material for the Army. AMCCOM will provide information and guidance to TEAD to prevent violations of Federal regulations and to ensure safe transportation and burial of the material. Shipments are made only upon- authorization by AMCCOM. Burial Costs ~will be paid by'AMCCOM. Packaging and transportation cost will be borne by TEAD.

b. Solid DU penetrators from demil activities will-be stored by TEAD or transferred to an NRC or Agreement State Licensee who is authorized to receive them. Any unwanted material is expected to be solid and is not expected to involve the ges.aration of liquid, dust, mist, vapor or gas. Disposable protective clothing and swipes can be expected to become contaminated.

c. The requirements of 10 CFR 40.36 (Financial Assurance & Decommissioning) do not apply to TEAD since the DU is.not in-a dispersable form. Munitions containing DU are not expected to contaminate anything including the package or container.

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Application. (NRC. form 313) .to Renew Materials License #SUC-1391 $ Tooele Army-Depot, Utah

ITEM #12: LICENSE FEES. ' a. The NRC assesses an annual fee, with a surcharge, to- federal agencies. The fee is paid by Tooele Army - Depot . when ' billed. : '

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Tooele Army Depot, Utah '

ITEM #10: RADIATION SAFETY PROGRAM.

1. POLICIES:

a. The Radiation Protection Program for Tooele Army Depot (TEAD) personnel will be consistent with Nuclear Regulatory Commission, Department of the Army, and U.S. Army Material Command regulations and directives. All operations involving ionizing radioactive materials or radiation producing equipment will be conducted so as to maintain radiation exposures to personnel as low as reasonably achievable (ALARA). In no case will established exposure limits be exceeded,

b. TEAD will maintain adequate facilities, equipment, procedures and trained personnel commensurate with the type and quantity of radiation sources on-site. Standing Operating Procedures (SOPS) , will be maintained for all radiological operations. '

c. Transportation, storage, control and disposal of radioactive materials will comply with all applicable regulations established by the Nuclear Regulatory Commission, the Environmental Protection Agency, the Occupational Safety & Health Administration, the * Department of Transportation, the Department of the Army and the U.S. Army Material Command.

2. RESPONSIBILITIES:

a. The Commander of Tooele Army Depot will ensure that the radiation protection effort is commensurate with the hazards present. The Commander will ensure that local radiation safety policies and procedures to mitigate these hazards are established and annually updated. The Commander will ensure that adequate resources (staffing equipment, funding, training, and support) exist to maintain a formal radiation safety program which complies with all applicable regulations. The Commander will appoint a radiation protection officer and will appoint a member of his staff- to preside over the radiation control committee.

b. The Radiation Control Com.ittee (RCC) will advise the Commander on matters impacting the radiation protection effort. The RCC will ensure that procedures for procurement, storage, use and disposal of radiation sources are established and reviewed annually. The RCC will review all radiation incident reports, employee concerns, training programs, dosimetry / bioassay reports,

licenses /DARAs, corrective action with respect to radiation ; surveys, qualifications of users of radioactive sources and- radiation safety regulations.

, c. The Radiation Protection Officer will implement and manage the Radiation Safety Program at TEAD. The RPO will advise the

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Commander and RCC of compliance with NRC licenses; report unsafe c radiation working conditions; conduct radiation safety training; conduct an annual review of all radiation SOPS, programs and policies; ensure operational compliance with those SOPS, programs and policies; manage the personnel dosimetry program; perform radiation surveys; and prepare / submit applications for NRC licenses and DARAs. ' d. The US Army Health Clinic will perform medical examinations and bioassays for radiation workers as prescribed in Army Regulation 40-14 upon the recommendation of the RCC. The. Clinic will provide medical support to any radiation response effort. ' The Clinic will provide one member of the RCC.

e. The Chief of the Fire Department will provide emergency support to any radiation incident and ensure that emergency personnel are trained to handle radiation emergencies. On member of the RCC will be from the fire department. The Fire Chief will receive quarterly, from the RPO, a copy of the radioactive material inventory listing showing radionuclides, quantities, locations and possible hazards to emergency personnel.

f. Operations Managers & Supervisors responsible for operations involving radioactive materials or radiation producing equipment will, under the direction of the RCC & RPO, ensure that all aspects of the Radiation Safety Program and all applicable regulations are complied with. Operational Managers will ensure the all regulatory and SOP requirements are strictly enforced and that all radiation workers use the necessary personal protective equipment, are under medical surveillance, wear personal dosimetry and are properly trained. Operational Managers will ensure that emergency procedures are established and will ensure that any emergency or non-compliance is properly and promptly reported to the RPO & RCC.

3. TRAINING:

a. Radiation workers will receive initial and annual training as specified in 10 CFR 19.12 and 29 CFR 1910.96. This training will include information regarding potential radiation hazards on-site, biological effects of radiation, principles of ALARA, precautionary measures such as personal protective clothing, monitoring such as bioassays and dosimetry. emergency procedures, regulations and SOPS, radiation detection and measurement, procedures for reporting unsafe conditions or acts and the employees right to exposure records.

4. PERSONNEL MONITORING:

a. Personnel will not receive any exposure greater than the limits set in 10 CFR 20. The limits to radiation workers in restricted areas are listed in rems per quarter: whole body 1.25, hands & feet 18.75, skin 7.5. Radiation into an unrestricted area may not result in an exposure to any person greater than .5 rem per year.

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b. When it is determined that the potential exists for any individual to receive ten percent of the allowable dose limit, dosimetry is required to measure external dose and . bioassay is required to determine internal dose.

c. Self-reading pocket dosimeters will be used to supplement the dosimetry badge (TLD) in areas where the exposure rate is greater than 100 mrem per hour or where open area radiography is being preformed.

d. In cases where exposure readings are not available due to loss or failure of the dosimeter, the RPO must assign an administrative dose in accordance with 10 CFR 20.

e. Radiation workers will be given preplacement and termination examinations which will include medical history, radiation exposure history, physical examination, and complete blood count. Ophthalmic examinations will be performed on employees exposed to ' neutrons or high energy beta particles. Bioassays will be performed to establish baselines for workers exposed to unsealed radioactive sources. Radiation workers must be reexamined yearly during employment.

f. Visitors and personnel on temporary duty for fewer than 30 days do not require a medical examination if they will not be exposed to a whole body dose equivalent greater than: 2 mrem in any hour or 50 mrem in any 7 consecutive days or 100 mrem in a calendar year. g. Dosimeter Application and Record of Occupational Exposure (DD Form 1952) will be used and maintained. The automated dosimetry reports prepared by the Army Ionizing Radiation Dosimetry Center may be used in lieu of DD form 1141 for the recording of external { exposures. DD form 1141 must still be used for internal exposures. 1 -l 5. SURVEYS

, a. Routine radiation surveys will be conducted, under j representative conditions, monthly where radioactive material is ' used. Secured storage areas, exclusively for radioactive material, which are not disturbed may be surveyed every three months. Surveys will be performed using portable survey instruments, smear samples or air samples, as appropriate, to assess radiation and j contamination levels. Random samples must be taken in radiation areas and areas, such as restrooms and lunchrooms, that are frequented by employees.

b. Maintenance operations or work involving radioactive items which may release radioactive materials must be monitored for the amount of radioactive particulates released. Monitoring will ] consist of continuous air monitoring, air sampling, surface - contamination wipes and survey with an appropriate detector. Air sampling must be performed prior to venting or airing-out any building. Stack monitoring must be continuous whenever air is

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~ . AWB Sl S92 vented outside. The permissible dose concentrations in 10 CFR 20 appendix B will not be exceeded. Such a monitoring program will be established by the RPO with the approval of the RCC.

c. Every survey record will contain a drawing of the area ' surveyed, location and type of measurements, measurement results, instruments used, instrument calibration date, background counts, name and signature of surveyor, lowest level of detection of the instrument used and action required to correct any discrepancies.

d. Air monitors will be required in areas where maintenance operations are conducted involving tritium, or where the total quantity if tritium in storage exceeds 1000 curies. The monitor alarms must be set no higher than 5 microcuries per cubic meter.

e. TEAD will maintain the following types of instruments for use in conducting surveys: Geiger / Muller beta /gama survey meter, alpha survey meter, alpha / beta proportional counter, ionization survey meter (beta / gamma), liquid scintillation counter for low energy , beta. The survey instruments will be sent to Test, Measurement & diagnostic Equipment (TMDE) in either ogden Utah or Sacramento California for calibration in accordance with TB 43-180 on 90 day cycles. Any survey instrument sent out for calibration will have a back-up instrument so that an instrument with valid calibration is always available. For laboratory instruments, quench curves, voltage plateau charts, control charts from standards and counting efficiencies will be run monthly.

, 6. STORAGE AND HANDLING: a. Specific areas will be set aside for the exclusive and secure storage a radioactive materials. Radioactive' items will not be stored with explosives (except DU) , photosensitive items, flammable i materials, food products, or other incompatible items. |

b. A physical inventory of all radioactive materials in storage ,

will be conducted at least annually. Inventory records will i contain item nomenclature, national stock number, special control j item code, radionuclide, original or maximum activity, chemical and i physical form, storage location, number of items and missing items. |

7. TRANSPORTATION-

a. TEAD RPO will ensure that all shipments of radioactive material are monitored in accordance with 49 CFR 173.443. The amount of non-fixed radioactive contamination must not exceed 220 dpm/cm2 for uranium, thorium or beta-gamma emitters. The limit is 22 dpm/cm2 for all other alpha emitters. SDSTE form 3723 will be completed to document the survey and a copy will be sent with the shipment. Packaging and labeling will be in accordance with 49 CFR and 10 CFR 71. Radioactive material may not be shipped with food stuffs, animals or explosives (except DU).

b. TEAD RPO will ensure that incoming radioactive materials are .

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monitored in accordance with 10 CFR 20.205 within three hours of receipt. The shipper and HQ DESCOM will be immediately notified if the removable contamination limit of 220 dpm/cm2 is exceeded. TEAD Supply SOP #385-11 governs the receipt of packages containing radioactive material.

8. DISPOSAL:

a. Radioactive material will not be sold, donated or transferred to persons without an appropriate NRC -license. Unwanted radioactive material will be disposed of in accordance with U.S. Army Armament, Munitions, & Chemical Command AMCCOM pamphlet 385-1. (Handbook for Disposal of Unwanted Radioactive Material). AMCCOM has been designated as the agency responsible for the safety disposal of radioactive mv erials for the Army. AMCCOM will ' provide information and guidance to TEAD to prevent violations of Federal law and to ensure safe transportation and burial of the material. Shipments are made only upon authorization by AMCCOM. Burial costs will be paid by AMCCOM. Packaging and transportation ' costs will be paid by TEAD.

9. EMERGENCY PROCEDURES: a. Emergencies involving radioactive material may include fire, overexposure to personnel, release of material, loss of source or , transportation accident. The RPO will be notified immediately and will take charge if any of these events occur. Any of these' events will be reported to HQDESCOM telephonically then to the NRC if required by 10 CFR 21. Any release or fire involving radioactive material will be handled like any hazardous material _ emergency. 7 All fire fighters responding will wear Self-contained-breathing- ' apparatus and other required protective clothing. The RPO (using the computer program DUDOSE from PNL) and the chief of the Safety Division will determine the safe evacuation distance. Contamination prevention and decontamination procedures will be employed. Air monitoring, air sampling, soil / water sampling, surface wipes and instrument surveys will be conducted as appropriate. Employees will not return to the work area until the area is released by the RPO with guidance from HQDESCOM.

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NRC MATERIALS LICENSE #SUC-1391, Suplement 1.

AED REPORT 07-89

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AMMUNITION EQUIPMENT DIRECTORATE TOOELE ARMY DEPOT UTAH 84074-5004 :

DEMILITARIZATION OF DEPLETED URAh2UM DEVICES

22 MARCH 1989

PREPARED BY: CONCURRED BY: ,

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I M__ __- , R. JfY L. BISHOP - GAIL H. CHRISTIANSEN Chemical Engineer Radiation Protection Officer ,

REVIEWED BY: APPROVED BY:

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; _- __ _' / DR. R. DO,pGLAS MIELSEN , X M. ZAdGG /p[ Chief, Chemical Systems irector for A u 'ti W Equipment Engineering Division

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.' ~ ; DEMILITABIZATION OF DEPLETED URANIUM DEVICES ''

Amensnition Equipment Directorate, Tooele Arat* Depot, ' Utah ; Jay L. Bishop .PhD ~ ,

22 March, 1989- . .

SUIBl&RY ! The four main hazards related to work' with depleted uranium (DU) are- *

external radiation exposure, internal radiation exposure,. toxicity and - . pyrophoricity. The scientific basis for understanding the hazards is given in this report along with descriptions of proper safety procedures. and

equipment for demilitarization of military devices which contain depleted ; uranium. Improper procedures can cause serious injuries, but these can be ;i avoided very easily. Strict adherence to the recommendations is expected to provide safe operations free of unf avorable incidents or after effects. ' Military uses of uranium are outlined and examples are given. The advantages of depleted uranium, namely high density,. strength and low cost,'- are compared with the properties of competing . materials. .The Nuclear Regulatory License, and regulations which govern depleted uranium work are ; explained. Important . literature sources are cited for use in standardization of operations and in compilation of SOPS. General ; principles for DU handling and demilitarization are given,- and specific examples of- protocol are noted, some of which apply only .to TEAD projects. _.

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TABLE OF CONTENTS PAGE ,

SIGNATURE PAGE ...... 1 SUMMARY , ...... 2 TABLE OF CONTENTS ...... 3 LIST OF TABLES AND CHARTS ...... 4 INTRODUCTION DEMILITARIZATION REQUIREMENTS ...... 5 NATURE OF DEPLETED URANIUM ...... 5 RISKS FROM HANDLING DU IN DEMILITARIZATION PROCESSES EXTERNAL RADIATION EXPOSURE ...... 6 INTERNAL RADIATION EXPOSURE ...... 6 TOEICITY ...... 6 PYROPHORICITY ...... 6 NRC LICENSE FOR HANDLING RADIOACTIVE MATERIALS ...... 6 MILITARY USES OF URANIUM NUCLEAR USES ...... 7 CONVENTIONAL USES ...... 7 PROPERTIES OF DU AND COMPETING MATERIALS ...... 8 TECHNICAL PRINCIPLES FOR UNDERSTANDING RISKS AND PROTECTIVE MEASURES DEFINITIONS ...... 11 DISINTEGRATION RATES, TWO INDEPENDENT SERIES OR CHAINS . . . 12 COMPOSITION OF URANIUM , ...... 13 - EVALUATION OF RADIATION HAZARDS ...... 13 RADIATION BANDS OF CONCERN FOR DU WORKERS ...... 14 PROCEDURES AND EQUIPMENT WORK AREAS ...... 16 Outer work room and restricted work room ...... 16 Air conditioning ...... 17 Air filters ...... 17 Air monitors ...... 17 Smear samples ...... , . 18- MACHINE REQUIREMENTS ...... 18 - PERSONNEL SAFETY PROVISIONS ...... 19 Causes of the four main hazards; protective measures . . . 19

MONITORING METHODS, EXPOSURE LIMITS, SPECIAL PRECAUTIONS . . 21 Personal dosimeters ...... 21 Exit tester for hands and feet ...... 21 Measurement of internal exposure ...... 22 Air monitors ...... 22 Monitoring of surface contamination ...... 22 Special clothing ...... 22 Respirators ...... 23 ! Exposure limits ...... 23 | SOURCES OF INFORMATION FOR COMPILATION OF SOP'S ...... 23 i i I

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APPENDIX

- SHIPPING OF DU PARTS AND SCRAP ...... / . E, 24 ADDRESSES FOR LABORATORY SERVICES'...... - . . 24- CHEMICAL SYMBOLS' ...... 25 THE TWO URANIUM DECAY SERIES ...... 25 ' ABBREVIATIONS ...... 27 REFERENCES ...... ' .~. 28'

. .- . , LIST OF TABLES AND CHARTS-

PROPERTIES OF DU AND COMPETING MATERIALS ...... 8 DISINTEGRATION RATES OF ISOTOPES, TWO INDEPENDENT CHAINS . . . . 12 COMPOSITION OF URANIUM ...... 13 RADIATION BANDS OF CONCERN FOR DU WORKERS ...... 1. . 14 CHEMICAL T0XICITY ...... 20 EXPOSURE LIMITS, PERMISSIBLE DOSES ...... 23 THE TWO URANIUM DECAY SERIES ...... 26'

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' INTRODUCTION

DEMILITARIZATION REQUIREMENTS

The military storage system presently includes munitions and other devices containing DU which exhibit radioactive characteristics. Storage, demilitarization and other handling of these items requires a license from the Nuclear Regulatory Commission (NRC) issued to each installation which is to conduct such operations. Each item to be demilitarized requires an SOP with sufficient detail to provide safety against all potential hazards. This report 1 outlines the information necessary for understanding risks of handling DU devices, and writing 50P's for their demilitarization, to include the following:

1. Risks from handling DU in demilitarization processes.

2. NRC license.

3. Military uses of uranium.

4. Technical principles for understanding risks and protective methods.

5. Procedures and equipment needed for storage, demilitarization and other handling of DU items, with details for environmental protection, safety of operators, pertinent regulations, and treatment of machinery and residues after the demilitarization is complete.

6. Sources of information for compilation of SOP's.

NATURE OF DEPLETED URANIUM

Depleted uranium is a by-product of the nuclear industry. Natural uranium ' is a mixture of 99.3% non-fissionable isotope uranium-238 and 0.7% fissionable uranium-235, with traces of other isotopes and elements. ; Uranium with the uranium-235 content enriched to 3% is obtained for nuclear energy reactors and further treatment for nuclear weapons by a disproportionation process which leaves the depleted uranium behind.***A' Other names for it are tuballoy, staballoy, D38 (common in DOE installations), and DU (a common D0D abbreviation). Natural uranium and DU thus differ only in the minor components. They have essentially the same metallic properties. Because of the important nuclear use of uranium-235, the enrichment by-product DU has become readily available; for every kilogram of uranium enriched to 3% uranium-235, five or six kilograms of DU are obtained, which contain only about 0.25% uranium-235. DU is used where there is a need for the unusual mechanical and chemical properties shown by uranium in general, namely high density (2.5 times that of iron), machinability, metallic strength and pyrophoricity.* ' For most military uses of DU high density is the important property, with tungsten being the least costly competitor for metallic strength, and lead being the least costly competitor for bulk shielding of radiation. See the following chart which compares density and other properties of competing metals.

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RISKS FROM HANDLING DU IN DIDELITARIZATION PROCESSES , Dangers of DU are widely misunderstood. The term * depleted * refers to the f act that most of the uranium-235 has been extracted and does not mean that - the radiation has been depleted. Impurities which would ' contribute the most dangerous radiation are removed in the process of DU production.' But

they will be left .in the DU when the laser enrichment process becomes the~ s main method for producing uranium-235. Currently,' the- handling of depleted uranium does not present a complex safety problem; it is the least - hazardous long life radioisotope. Sound industrial hygiene practice ' affords adequate protection.* More details concerning ;these risks, and - precautions for them are given in later sections.

1. DU radiation is npot, hazardous externally, and newly. milled blocks of DU are handled safely without gloves at DOE facilities. -. Radiation from DU is both low intensity because of the long half-life of uranium, and low energy as alpha particles. Leather gloves and special glasses are sometimes recommended for long-term handlers, to stop all the alpha radiation and half of the minor beta radiation. Hazards of long-term storage are easily controlled.

2. Internal human exposure to DU is, a hazard. DU is excreted so slowly " that internal organs are in danger from both its direct radiation and that of its long-term disintegration products.

3. Internally DU is also a dangerous chemical poison.

4. DU is pyrophoric in finely divided forms, 'giving high intensity- fires, as well as extreme danger of '2. and 3. from the fumes.

, NBC LICENSE FOR HANDLING RADIDACTIVE MATERIALS Possession of more than 15 pounds of radioactive material ordinarily requires a license from the U.S. Nuclear Regulatory Commission (NBC). Regulations concerning radioactivity are outlined in Title 10 CFR.** Users of DU for the benefit of its high density only are not required to obtain a license, as long as they register with the NRC, perform no. mechanical , * reforming or metallurgical treatment on the DU, and dispose of it to a licensed recipient. There is no regulatory control whatsoever for the .use of DU as counterweights or balance weights in airplanes, helicopters or missiles, or as shielding in shipping and storage containers, or in equipment for cancer therapy or industrial radiography **. (unless the user already possesses DU under a specific NRC license). -

The TEAD materials license * (number SUC-1391) issued by the NRC was most recently renewed on 26 Apr 1988 and is good until 31 Aug 1992. It has been renewed or amended several times as needed since it was first granted 29

Jan 1981. It is important for this license to be maintained in active ; condition, being one of only two NRC licenses in the jurisdiction of the , U.S. Army Materiel Command (AMC) with such extensive coverage.. The TEAD ' permit allows possession.of up to 7.7 million pounds of DU alloy as components of military ammunition at the Tooele Army Depot location in ,

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Utah. The license specifically covers the handling, storage, and demilitarization of DU munitions and the storage of bulk DU. It also allows possession of up to 441 pounds of.DU used as shielding material in radiographic exposure devices, such as the Varian Linetron 200 linear accelerator, and covers this usage at the Pueblo Depot Activity, Colorado, which is part 'of the TEAD Complex with headquarters at Tooele Army Depot, Utah. The licensed material is to be used by, or under the supervision of Gail H. Christiansen or Mervin L. Beck of the TEAD Safety Office, who are specifically named with this stewardship by wording of the license itself. An NRC license at Savanna Army _ Depot Activity also allows demilitarization of DU munitions.a* The Savanna work SOP has many details which can servo as guidance, especially for operations preceding the removal of the DU.**

P MILITART USES OF URANIUM

NUCLEAR USES

DU is a by product from the production of fissionable uranium-235, which is extracted from uranium for nuclear uses because of its high nuclear capture cross-section. The main component of natural uranium is 99.3% uranium-238 which is not fissionable. The fissionable uranium-235 is enriched to 3% from its 0.7% natural concentration in uranium by various slow separation processes, the most common being gaseous diffusion.- Uranium hexafluoride is a crystalline solid at ambient temperature. It sublimes near its melting point of 64 'C, and is totally vaporous above 65 oC. Gaseous UF.. is diffused with pressure up to 20 psia through the walls of miles of porcus tubing with uniform pores less than two millionths of an inch diameter. Molecules of gas containing uranium-235 diffuse only slightly faster than those containing uranium-238, so thousands of cycles are necessary to gain an enrichment of only a few percent. The hexafluoride is reduced with :tydrogen to crystalline uranium tetrafluoride and then to uranium metal with magnesium (or calcium). Uranium enriched to about 3% is used in nuclear reactors of the type most common in USA, or is further concentrated in processes for making nuclear munitions. Ultracentrifuge and laser isotope separation processes are now being perfected to speed up the enrichment process considerably.

CONVENTIONAL USES

The following table compares properties of metals which compete with DU. Tungsten, DU and their alloys listed in the table are used more than other metals for the military applications of concern in this report. Physical properties for the table were compiled from several sourc e s,'' **** *** * 25.* * 2 8 Density, mechanical properties and resistivity values for base metals are at 20 *C. Low hardness values for unalloyed metals are for the annealed state; literature hardness values given in various scales (Vickers, Brinell, Rockwell-B & C, Knoop) were converted to the Vickers scale for comparison. Prices are spot quotes, or base prices for bulk stock.**'** Tungsten price is for pressed and sintered billet. The associated raw unpressed tungsten powder price is 89.53/lb. The DU price is the base rate for unalloyed derby metal as obtained from reduction of UF4 green salt. The metals are listed in the table in order of density,

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b the property of greatest military interest. Uranium is less costly than all other metals as dense, and is easier to fabricate than tungsten and thenlun Some other high density metals like gold and platinum lack strength and are costly as well. In some military uses both high strength and high density are needed, in which cases rhenium and tungsten are alternatives to~ DU. But rhenium is radioactive itself* and far more costly 28 than DU. Tungsten must be pressed and sintered from the powder, whereas DU can be cast from the melted form.

PROPERTIES OF DU AND COMPETING MATERIALS

Tensile Modul. Melting Hesis- 1987 Avg. Density Hardness Strength Elast. Temp. tivity Base Cost Symbol Name g/ca" Vickers MPa GPa *C n0.m */lb

Pt platinum 21.45 37 125 170 1769 106 6707 Re rhenium 21.04 122 1200 460 3180 193 600 Au gold 19.32 27 103 78 1064 23.5 5359 W tungsten 19.25 315 1825 410 3410 55 24.9 W-7Mo 18.6 312 960 405 70 40.0 W-4Ni-2Fe 17.85 292 920 305 34.0 U DU 19.05 92-250 450 172 1130 280 3.80 U-0.75%Ti 18.6 412 1650 1200 4.22 U-2%Mo 18.5 1600 1150 4.41 Pb lead 11.34 4 13 14 327 206 0.223 Ag silver 10.49 25 125 71 961 15.9 79.8 Cu copper 8.93 80 209 128 1083 16.7 0.679 Fe 1020 steel 7.86 122 440 205 1160 165 0.320 Fe 4140 steel 7.84 327 1075 200 1120 222 0.003 Heat treatment of DU alloys containing 3 to 6% titanium, molybdenum. niobium or zirconium has given remarkable properties, such as tensile strength as high as 2068 MPa.* The twc uranium alloys used most for

military purposes are shown in the above chart, with either 0.75% titanium , or 2% molybdenus Heat treatment then gives a wide variety of properties, ' including those at peak aging, the condition for uranium alloys listed in the chart. For ordnance use the standard treatment is heating at 850 C, quenching in water or oil, and aging at various temperatures from 350 to 450 *C.** These alloys also oxidize more slowly; U-2Mo oxidizes only half i as f ast and U-0.75Ti only 6% as fast as unalloyed DU. Other corrosion protections in use are epoxide paint and plating with other metals such as i copper, nickel and cadmium. Xinetic penetrators made with these DU alloys : are not usually coated, yet have storage lives over ten years and have j passed all atmosphere exposure tests. Nevertheless, adequate protection to i personnel must be provided for work on such munitions, in case any of them have had much uranium corrosion during unknown storage conditions in the past. If cost is more important than density in a particular application, then certain steels are competitive. For example, consider containers that will shield the radiation of radioactive contents. Fairly low cost is a benefit of 4140 and other steels, which if constructed three times as thick as the

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tungstan or DU analog can provide as much mass for shielding 'and at least as much strength. Tungsten has the highest melting point of all metals and is not cast from melted form. Powder metallurgy required for tungsten does not commonly provide inexpensive slabs larger than about 8 by 20 inches.** So DU is widely used, as it can be cast from melted form up to 6 tons at a time.* Some applications for which DU and tungsten are popular require as much mass as possible in a small space, e.g., ballast. Some uses require both- strength and high density, e.g., projectile penetrators. Lead has lowest cost but also lowest strength as shown by the chart, and requires 68% greater thickness than DU to equal the same mass. Even for small sized applications like shielding for instrumental radiation source lamps, DU is often preferred. The higher melting points of DU and tungsten are a favorable characteristic for uses in heated conditions.

DU conducts electricity about as well as iron. The electrical resistivity at 280 nQ.m is an order of magnitude less conductive than that of copper, silver or gold, but still f ar more conductive than carbon electrodes at 13,750 nQ.m resistivity. DU has some uses in this field, described below. The enrichment process to obtain uranium for nuclear uses gives more than five times ** as much by-product DU as the enriched uranium main product. This large amount of DU lef t behind after extraction of the uranium-235. content is essentially the only source of uranium for non-nuclear purposes. DU from the gas diffusion process is thus high purity uranium-238 which is nearly depleted of other isotopes and radioactive daughters. Uranium is used in conventional munitions because of the advantages of its physical and mechanical properties, despite its slow nuclear disintegration. The properties that account for most of the military and industrial uses of DU are its high density, pyrophoricity, strength, ductility, machinability, and special properties attainable by heat treatment and alloying, such as hardness and resistance to oxidation. Depleted- UF. which is reduced to UF4 and then to the metal supplies DU in a cylinder form called a derby,** which weighs from 300 to 1000 pounds, and serves as the starting material for the fabrication of nearly all DU products. DU is melted under a protective blanket of inert atmosphere, to prevent reaction with air. Physical DU forms are available most commonly from casting and milling, but DU is also wrought hot and cold, extruded, rolled, drawn, turned, swaged, etc., to provide plate, bar, rod, tubing, billet, etc.

Uranium pyrophoricity is an advantage in some military uses.*>'' It is the most pyrophoric of all elements.' N1 As a center probe in armor piercing munitions, DU has a primary advantage with its high density. But in the process of armor penetration it also burns as it penetrates, and spreads fire inside the armored enclosure.' Rhenium powder is flammable if heated,- but not pyrophoric at ambient.*** DU use in armor piercing projectiles accounts for more than any other application of DU,"* as well as for the main purpose of the TEAD NRC license.**

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Military uses for DU include most of the following applications, of which items 1, 2, 3, 4, 7, 9 and 10 relate to materials in . the TEAD NRC license.

2 1. Projectile; armor piercing rounds constitute by f ar the largest single use of DU;** the alloy density, strength, hardness & cost are competitive with tungsten; postpenetration pyrophoricity is a unique advantage of DU projectiles; some examples are: 20mm Navy Phalanx penetrator for ship to ship missile defense, 30mm Air Force GAU-8/A penetrator for A-10 aircraf t against armored tanks,105mm M833 antitank cartridge for M68 cannon,120mm M829 cartridge for M256 cannon.

2, Projectile, M-101 spotter round; high density gives proper polar moment of inertia to simulate Davy Crockett round trajectory.

3, Special purpose artillery shells; high density, high strength DU alloy center body structural member gives flight stability.

4. Pyrophore; as a component of munitions which release DU in a finely divided form, uranium immediately bursts into flame because of the high surface area in air, and burns at a hign temperature.

5. Ballast; up to 6 tons of DU can be cast at once (as opposed to the maximum size of tungsten castings of about 100 pounds,54 limited by powder metallurgy), DU consumption~ for ballast and counterweights had grown to 250 tons per year by 1976;* used for vibration dampeners in aircraf t and metal milling machines, ballast in flywheels and heavy machinery, rotor rims, payload simulation in missiles and vehicles.

6. Counterweight; high density allows low volume localized positioning , for gimbal weights and other counterweights in aircraf t control surfaces, missiles, general machinery and gyro-rotors; for example, each Boeing 747 uses 3300 pounds of DU.*

7. Radiation shielding; DU is a near ideal shielding material for gamma, X-ray and other sources such as Ir-192, Co-60, Cs-137 for isotope radiography, as containers for irradiated fuel tanks, Navy atomic energy refueling systems; the combination of high strength and high density make DU far superior to lead in meeting regulated specifications, lead has little strength and requires a 68% thicker layer to equal the same mass of uranium.

8. Catalysts; patented processes for using DU catalysts in chemical industries of military interest had reached a demand of 200 tons of DU per year by 1978.*

9. Ordnance alloys; New methods for making DU alloys with molybdenum. zirconium, titanium, niobium, vanadium, aluminum or other substances have provided various materials with amazing properties, such as high ductility, or tensile strength beyond 300,000 psi (2068 MPa); Mil specs now govern alloy quality for

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military uses, and extremely high purity is now attainable; traces of carbon, iron, silicon and aluminum have marked effects upon metallic properties.

10. Electronic properties; DU is used with devices for special X-rays, ultraviolet radiation, radiation metering standards, impurity scavenging, negative temperature coefficient resistors, ionic centrifuge electrodes, shadow casting of electron microscope images, electron spectral transitions at specific wavelengths in fluorescent and non-fluorescent materials. 11. Chsmicals; uranium compounds made from DU have specific biological, chemical, or physical properties of value, including uses as stabilizers, hardeners and colorants for glasses and ceramics.

TECHNICAL PRINCIPLES FOR UNDERSTANDING RISKS AND PEDTECTIVE MEASURES

DEFINITIONS

Reference 4, p 1-1 to -22, contains the most complete list of definitions found in this study, which are pertinent to the demilitarization of military devices containing DU. See APPENDIX for additional definitions under ABBREVIATIONS, and for a description of use of chemical symbols. curie (C1): 3.7E10 disintegrations per second (dps).

Depleted uranium: Depleted uranium is purified ***U, and as such has less than the 0.7% *"U found in natural uranium (See DARCOM HDBK* p 1-6). In practice most DU has 0.25% *"U. Enriched uranium: Enriched uranium has a higher *"U content than the 0.7% occurring naturally. Uranium for nuclear power plants is usually 3 to 4% *"U, and for nuclear weapons is much higher. rad: Dose of 100 erg absorbed in 1 gram of body tissue. (Radiation absorbed dose.) rem: Dose of radiation to body tissue with the biological effect equivalent to that of 1 R of gamma or X ray. (Roentgen equivalent man.) roentgen (R): Ionizing radiation that produces 1 esu of positive or negative ions per 0.001293 grams of air (1 ml volume at 0 *C and 1 atm.). 1 R is also equivat.ent to 2.58E-4 coulombs of ions per kilogram of air. Limited quantity radioactive materials: DOT quantity exempt from most restrictive shipping rules, defined by radioactivity below limits specified in reference 19 part 173.421.

% Smear sample, wipe sample: Sample taken to measure presence of removable radioactive contamination on a surface, by wiping the surface with a soft paper for analysis. In demil work taken mainly to detect uranium oxide coatings and surface collection of radioactive dust.

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Source material: Ore, metal or other material with ,>0.05% total uranium plus thorium content. Special nuclear material: Enriched ***U, enriched ***U, plutonium, etc., except for source material.

DISINTEGRATION RATES OF ISOTOPES, TWO INDEPENDENT SERIES OR CHAINS.

Uranium-238 Chain Half-life Uranium-235 Chain Half-life

88*U 4.51E9 years ***U 7.1E8 years | I ***Th 24.10 days ***Th 25.52 hours , I I ' ***"Pa 1.175 minutes ***Pa 3.25E4 years \ | a**Pa 6.75 hours .

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***1J 2.47E5 years . I - . .

***Pb stable **'Pb stable

A complete version of the above chart is presented in the APPENDIX. Natural uranium is mostly the ***U isotope, with small amounts of ***U, ***U and traces of the daughter products of their decomposition. The half-lives and usual abundances of components in natural, depleted and enriched uranium are listed below under the heading COMPOSITION OF URANIUM. Uraniumr-238 decay proceeds through successive unstable elements including uranium-234, in a 15-step series, or chain that ends with stable lead-206 (* 'Pb). Uranium-235 decomposes in an entirely different 11-step chain of successive unstable elements ending with stable lead-207 (* 'Pb). Elements and isotopes in both chains include many examples that have rather short half-lives, and so also quite low concentrations. In each of these two series is an element near the top, that has a long half-life, which further minimizes the formation of significant amounts of subsequent isotopes (i.e., those following the intermediate with a long half-life). Although natural uranium contains all the components in these chains, DU is composed mostly of only ***U, ***U and ***U, because

other elements have been removed in refinement. , In DU at equilibrium, which is attained within 6 months, traces of ***Th and ***=Pa and other isotopes listed above are also present, having grown in from uranium disintegration. They are the short-lived intermediates in the conversion of ***U to ***U, and of ***U to ***Pa. At steady-state their continuous formation rates equal their continuous rates of disintegration, giving constant ratios of thorium to uranium and protactinium to uranium. **^Th and ****"Pa have measurable X-radiation at the DU equilibrium concentration to allow indirect determination of in-vivo DU exposure in workers by the use of an external monitor. It is

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indeed remarkable that thorium can serve this purpose at the low concentration it has in DU, a billionth of one percent (refer _ to the next ; two charts). This is easier to fathom in consideration of the steady state condition that the number of ***Th nuclei that disintegrate per I unit time equals the number that are formed from the preceding nuclide, ' and also equals the number of ***U nuclei disintegrating per unit time, or the number of disintegrations at any other . step in the same chain.

Thus a nuclide with a short half-life is present at equilibrium in low abundance but has one nucleus disintegrate for each parent nucleus that disintegrates. So the number of detected ***Th disintegrations is the same as the undetected number for ***U in the same unit of time. Although it takes only six months to reach steady state for ***Th, ***Th

and 85*Pa, it would take over a million years for total equilibrium of | all the nuclides in DU including asaPa and ***U and the others following | them. Steady state abundance of a nuclide in a particular sample depends on its disintegration rate, as well as the disintegration rate and concentration of the original parent in the chain (see the above chart). The number of atoms of that nuclide equals the number of atoms of the chain parent times the ratio of their half-lives (tTh/tU in the example below). The weight percent of that intermediate nuclide is then its percent population times the ratio of physical atomic weights. Atomic weights here are taken from Table of Nuclides 12.' **C being the reference with exactly 12.0 amu. For example, at steady state a sample of DU with 99.75% ***U contains 1.435E-9% ***Th by weight:

99.75% x 24.1 day (tTh) x 1 yr x 234.04358 amu = 1.435E-9% 4 ' 4.51E9 yr(tU) 365.2422 day 238.05077 amu.

COMPOSITION OF URANIUM The following chart indicates the percentages of components for typical examples of material, although depleted uranium has any amount of 8**U | 1ess than 0.7%, and uranium enriched in ***U has any amount over 0.7%. '

Main Natural Depleted Enriched Nuclide Half-life Emissions Uranium Uranium Uranium ) ***U 4.51E9 yr alpha 99.273910.0007% 99.75% 97.01% | ***U 7.13E8 yr alpha, gamma 0.720410.0007% 0.25% 2.96% ***U 2.47E5 yr alpha,(gamma) 0.005710.0002% 0.0005% 0.03% ***Th 24.1 day beta, gamma 1.43E-9% 1.44E-9% 1.40E-9', ***"Pa 1.17 min beta gamma 4.81E-14% 4.84E-14% 4.70E-14% ***Pa 6.75 hr beta, gamma 2.17E-14% 2.18E-14% 2.12E-14% **2Th 25.5 hr beta gamma 2.89E-12% 1.00E-12% 1.19E-11% **2Pa 3.25E4 yr alpha, gamma 3.23E-5% (1.12E-5%

EVALUATION OF RADIATION HAZARDS The danger of radiation is generally its ability to ionize internal body chemicals, and to cause free radicals, with the associated bond cleavage and rearrangement of chemical structure. The effect is to burn the body

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. tissue, to tear apart the molecules that make' up the body,' and to reform . . bizarre chemical structures, which start mutant strains of chromosomes = in cell nuclei and lead to cancer. The NRC refers to radiation that is . , dangerous simply. as ionizing radiation. . The types of ionizing radiation from DU' are alpha, be' ta, gamma and X-ray. The latter two are similar, but- from different origins, X-rays are secondary energy transitions generated during reflection of electron beams ' or beta rays,. whereas gamma rays are emitted directly from the ' nucleus. Gamma' and X-radiation are listed together as gamma. The patterns of characteristic abundance and energy strength are sufficient to identify each radiative transition. The energies in million electron volts (MeV) are given in the . table below for major radiations from each type of nuclear : disintegration pertaining to DU. Only the radiations of concern for those who handle DU are listed t ere, and have been taken from a longer list in ' Table 2-4 of reference 3.

EADIATION BANDS OF CONCERN FOR DU WORKERS

Alpha MeV Beta MeV n- MeV DU Nuclide Half-life (abundance) (abundance) (abundance) . Uranium-238 chain:

***U 4.51E9 yr 4.15 (25%) -- -- 4.20 (75%)

' a**Th -24.1-day -- 'O.103 (21%) 0. 003 _ (3. 5%) O.193 (79%) 0.093 (4%) * j

' ***"Pa 1.17 min -- 2.29 (98%)** 0.765 (0.30%) 1.001 (0.60%) ,

***Pa 6.75 hr -- 0.53' (60%) 0.100 (50%) i 1.13. (13%) 0.70 (24%) 0.90 (70%) '

***U 2.47E5 yr 4.72 (28%) -- 0.053 (0.2%) 4.77 (72%)

- Uranium-235 chain:

***U 7.1EB yr 4.37 (18%) -- 0.144 (11%) , 4.40 (57%) 0.185 (54%) * ; 4.58 (8%) 0.204 (5%)

'' ***Th 25.5 hr -- 0.140 (45%) 0.026 (2%) O.220 (15%) 0.084 (10%) 0.305 (40%) Demil of munitions containing DU does not present the risk of exposure to all radiation types present in uranium ore. Types present in DU are those

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from the three uranium isotopes it contains, and from the non-uranium j nuclides that grow in after the extraction of the DU. After 6 months when i they have reached steady state, nuclides then in sufficient concentration | to require radiological controls are thorium-234, protactinium-234m and | protactinium-234 of the uranium-238 chain,- and thorium-231 of the | uranium-235 chain. Protactinium-234m converts 99.87% directly into j uranium-234, but the 0.13% that goes through protactinium-234 is i significant at steady state because ***Pa has a half-life nearly 350 times that of ***"Pa. The long half-lives of the next products in those chains, thorium-230 following uranium-234 in the uranium-238 chain, and protactinium-231 in the uranium-235 chain prevent significant accumulation of other decay products. Radon gas is a decay. product of radium in each of the two uranium decay series but at expected amounts of less than 0.01 picograms per munition is not a cignificant hazard even after long periods of storage. The munition compartment containing DU will be opened near an air exhaust port anyway in case radioactive dust is present, thus any radon will also be drawn out.

When DU by product from the laser enrichment process becomes available, it will have a much higher specific activity than DU from present processes, because the laser enrichment will separate out essentially just the uranium-235 and leave all other impurities with the DU that are removed from it in the present gas diffusion process.* SOP's written for DU , munitions manuf actured by the new process will have to take into account the increased radiation level. DU from the laser process will be identifiable by the increased specific activity, but careful labeling of those batches will also be expected. . i The primary radiation from uranium atoms is alpha particles that cannot penetrate the skin. These are atomic-mass-4 helium nuclei *He** that are stopped by matter as slight as a paper wrap. Beta particles from the decay chain are not a significant external hazard. For long-term handling, use of leather gloves and special glasses may be considered as they will reduce the beta radiation by 50%. After an oxide layer collects on bulk DU metal, gloves are recommended to eliminate personnel contamination. For this purpose DOE handlers prefer thin cotton gloves. Appearance of oxide layer is described in the Internal radiation exposure section of PERSONNEL SAFETY PROVISIONS.

Internal DU exposure cannot be measured by direct radiation from ***U atoms, because that_ radiation is absorbed by the tissue immediately around it. For the same reason the greatest radiation danger from internal DU is the alpha radiation, because it is totally absorbed by the tissue. Absorption of the beta radiation from the other isotopes is concentrated in the immediate half-inch of tissue. The resulting ionization of tissue chemicals leads to corruption of chemical structure and cell mutation. This is particularly ominous in the lungs, intestines and liver. Internal DU exposure is detected most conveniently by an indirect method, such as the monitoring of one of the several gamma bands present at the steady state (i.e., DU at least 6 months old). The most common for this purpose is the 93 kev X-ray band from the ***Th daughter. The 63 kev ***Th band and the 185 kev ***U band are also used (see above chartO, and to a lesser

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negative air pressure relative to the next outer enclosure, to provide a slight air flow into it from the outer work room.

The outer work room has much less control than the restricted area, but in turn will be maintained at a negative pressure relative to the outside of the building. This room is used for opening crates, removing wrappings, and dismantling devices down to the enclosure which contains the DU. But : the DU enclosure itself is to be opened in the res;ricted room, not the outer work room.

Normally no alpha or beta radiation and very little gamma radiation is expected from material and devices in the outer work room where packages are first opened, but if there is a possibility of broken devices within the packages some care is indicated. Each layer of packaging or containment is to be scanned quickly with a hand held radiation scanner (such as the Eberline E-120 Pan Probe). If unexpected radiation is detected, all active materials will be taken immediately into the restricted work area, and ventilation in the outer work area will be surveyed until a steady innocuous stream is confirmed.

Air conditioning. Work rooms should be ventilated and kept at a negative pressure relative to outer enclosures. Air flows from the outside environment into the outer work room, and from there into the restricted work area. Exhaust flow rate from the restricted work area is between 100 and 150 sefm. An exhaust stream.is to be positioned directly where DU devices are opened to axpose the compartment containing DU.

Air filters. Special air filters are required to treat the air which is exausted to the outside from the disassembly machine and from the restricted work room during demil work periods. Specifications for the air filters are published,8* and examples are already installed at many- DOE facilities, where advice and contract references are available. So-called ' absolute filters' are used for exhaust ventilation systems, with a calibrated filtering efficiency of 99.97% on 0.3 micron sized particles in the standard diocty1phthalate (DOP) test. An electro-optical system ' sensitive to concentration variance of 0.001% is used to test the filters in a stream with 40 grains per 1000 cubic feet of air. Maximum allowable penetration is 0.03%.*

Air monitors. Air breathed by workers and also air streams exhausted to the environment are to be circulated continuously through monitors capable of detecting a surge of radioactivity and setting off an alarm. A sampling circulator may also be used to document the average weekly radiation level. This circulation does not require all room air supply to go through the sampling absorbant, but rather a side stream of metered volume is put through the sampler continuously. Background levels should be established in the work room air before DU work begins. Much detail concerning air monitors is given in reference 3, pages 5-1 to 5-53. The samples from the worker air and exhaust air are to be analyzed weekly to determine the average radioactivity level. Air brer,thed by the workers should not contain higher concentrations of radioactive nuclides than the values shown e in 10 CFR 20,2* Appendix B, Table I. Exhaust air released to unrestricted -

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areas is not permitted to 1 concentrations of radioactive nuclides greater than those shown in 10 CFR 20,** Appendix B, Table II, on a basis averaged over a year or less. Table II values are generally about 4% of the values in Table I for air concentrations breathed by the workers in the restricted areas. OSHA regulations stipulate an allowable maximum of 0.05 mg/m3 of soluble uranium compounds and 0.25 mg/m3 of ' insoluble uranium compounds in workers' breathing air for 8 hours exposure per work day.2, More detailed information on worker exposure is available from the ' International Commission on Radiation Protection (ICRP).** The American Conference of Governmental Industrial Hygienists (ACGIID specifies a short term (15 min avg) exposure limit (STEL) of 0.6 mg/m3 for uranium compounds.** and supports recommendations on ionizing radiation exposure ' from the National Bureau of Standards and the National Council on Radiation Protection (NCRP), which is chartered by the U.S. Congress.**** Smear samples (wipe samples). If there is periodic release of uranium oxide dust into the air, it will become concentrated on upper surfaces as it settles. Smear samples further concentrate it to make detection easier. This is done by wiping a surface with an absorbent paper, which can then be checked with a scanner, or analyzed to a greater degree of sensitivity at a contract laboratory. Machinery, munitions, tables and floors in TEAD work will be sampled monthly with paper wipes, which will be analyzed by the TEAD BPO. Samples for high accuracy or third party objectivity could be s9nt to one of the laboratories for which the addresses are given in the Appendix. The Army dosimetry lab is capable, but would have to be funded. AEHA is capable and is mission funded. The U of U Environmental Radiation Laboratory is also capable.

MACHINE REQUIREMENTS In the TEAD project machining, drilling or cutting will not be allowed, unless absolutely necessary to accomplish the demil operation, and then only on the approval and suppvision of the TEAD RPO. Machining of uranium requires equipment with extra rigidity and ruggedness, with 50-100% greater capacity than tools for machining similar parts from steel. Should the DU parts of munitions for demil need to have holes or cuts made in them to facilitate dismantling, specific recommendations should be followed from reference 6, volume 3, pages 777-9 and 12 other references given there, concerning preferred tool steels, care of tools, rake angles, mrthods for drilling, tapping, grinding, cooling, handling of the millings, an.d etc. Each machine should be ventilated with a negative pressure intake where it handles the internal parts of the munitions. Each type of operation has specific recommendations for methods, given in reference 3, chapter 3. Machines that generate small particles or other forms of uranium with high surface area .per unit mass, will' be furnished with a continuous aqueous lubricant stream to keep air from contacting those high area surfaces directly, and to wash down such residues from the work surf aces into a reservoir where they are kept submerged, to guard against fire.

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extent other gamma bands which are present in DU at a known concentration relative to the uranium-238 at the steady state.***-** Uranium exposure is then estimated indirectly from its known equilibrium ratio with these other isotopes. Whereas alpha radiation within the body is undetectable outside the body, the high energy gamma bands from the other internal isotopes penetr.te body tissue with little absorption and are detected externally. Lung counts and whole body counts of gamma radiation from within the body are usually done at clinics where the counter can be provided with heavy shielding from background radiation. Heavy shielding makes more sensitive measurements possible and thus the detection of smaller amounts of lung exposure. Even so a long count lasting 30 to 60 minutes is necessary. DOE workers go to the clinic for regular measurements every 6 months or 1 year. The method is dependable _if care is taken not to misinterpret measurements in the following two specific instances.*P 4-32 7ggp{gg gg}gg gg g gggg higher temperature than does uranium and can become concentrated at the surface in molten uranium. hionitoring of uranium with such abnormally high surface thorium will give false high estimates of the uranium. Conversely, consider freshly purified DU which has not had time to form the steady- state amount of the "Th daughter. Exposure to freshly purified DU could thus go undetected or be estimated low until equilibrium is approached. It takes 3 months accumulation for the "Th, ""Pa and *Pa daughters to get near the known steady-state concentrations they reach within 6 months.

There are other alternatives to thorium-234 and uranium-235 gamma counts for external monitoring of internal exposure. The strongest beta band in DU is the one at 2.29 MeV (see an in chart on p 14). It doesn't penetrate the flesh to the outside of the body sufficiently for short time measurements, but if given enough time for the measurement it can also be used to monitor internal DU exposure. The counter must be well insulated from ambient radiation in each method in order to distinguish slight levels of exposure. Walls for such clinics must be thick and filled with steel or heavy metal to get the measurement time down to 30 minutes. Another alternative to gamma detection for monitoring internal exposure is the measurement of radioactivity in the feces, through which the uranium is excreted 2 to 5 times as much as through the urine." **-** All samples for one week for the person to be tested are collected in plastic bags and numbered consecutively. These are measured for alpha radiation from the three uranium isotopes 234, 235, and 238. Lung exposure can be detected this way immediately af ter exposure, even though total uranium excretion from the lungs is very slow, taking over 100 days. See the discussions of methods in the sections EVALUATION OF POTENTIAL HAZARDS and PERSONNEL SAFETY PROVISIONS.

J ' PROCEDURES AND EQUIPMENT

i WORX AREAS |

Outer work room and restricted work room. The work room where the devices to be dimilled are opened to expose the DU component, and where DU will be | handled is designated the restricted area. It will have 0.05 to 0.1 psi j

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Af ter the project is finished, the machinery and tools will be wipe tested for contamination that might be present from surface dust. If contamination exceeds limits given in AR 385-11 Table 4-3, the respective item will be decontaminated. Residue from the cleaning procedure will be included in the low level waste disposal.

PERSONNEL SAFETY PROVISIONS

Causes of the four main dangers, and protective measures against then

1. External exposure. Dangers of DU are widely misunderstood. Impurities which would contribute the most dangerous radiation are removed in the process of DU production. (They will be left in the DU, however, when the laser enrichment process becomes the main method for producing U-235. Batches from that process should be well identified to avoid confusion with low level batches.) Specific activity of DU is mild with only 3.6E-7 C1/g, which is about half that of natural uranium, and is equivalent to 13,320 atomic disintegrations per second per gram of DU. Alpha particles make up the primary radiation from DU and are not dangerous outside the body. In fact, newly milled DU items are handled safely without gloves at DOE facilities. Even large amounts in storage have no danger from alpha radiation if they have a wrap of some kind. It takes only a layer of paper to stop the alpha particles. Protection against the minor beta, gamma and X-radiation from large amounts in storage is easily arranged. . Externally the most energetic beta radiation will penetrate up to a half-inch of flesh, which can give skin burns if exposure is constant for long periods. TEAD workers who handle DU for extended periods should wear safety glasses and leather gloves for protection againct beta radiation. Otherwise the secondary risks listed next are far more important. '

2. Internal radiation exposure is potentially serious, i.e., from uranium that has gained entrance and become established inside the bodies of personnel, where it remains a long time before excretion. Refer to the discussions of internal exposure under EVALUATION OF POTENTIAL HAZARDS. Internally, uranium poses several dangers, such as the ionizing alpha ' radiation, and also radiation of the long term radioactive disintegration produc ts. Alpha radiation from the uranium itself, although innocuous externally, is dangerous internally. It is weakly penetratin, but strongly ' ionizing, a particular hazard in the lungs and intestines.* Beta radiation is not as ionizing as alpha, but much more dangerous internally than

outside the body. DU devices that have been in storage for many years , could have about 0.01 picogram of radon gas in the DU compartment. This '| will be of no consequence if there is an exhaust air port close to the work as each DU enclosure is opened, c,nd if workers are educated to keep the f ace away from the work when the enclosure is first opened.

,1 By far, the most important precaution in DU work is to guard against inhalation of uranium oxide dust. Freshly milled uranium metal as DU or , ' any other form oxidizes slowly on the surfaces exposed to air. Within a few days the silvery surf ace will have turned to a light brown, and in a ' month will be black from the layer of uranium oxide. That surface oxide is not always tightly bound and might be easily brushed off. Dust containing

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uranium oxide is easily taken into the body through air inhalation, through ingestion or oral contact with items that the dust can fall onto from the air or be brushed onto from direct contact with the uranium surface. .) Workers should not touch the f ace with hands. nor eat smoke or chew gum in ! the work area. Leather gloves are ureful for workers who handle oxidized uranium pieces. Gloves should r.a be taken out 'of the restricted area. Some DU forms have a higher hardness and oxidize slower (e.g., penetrator alloys). In some cases after storage over 10 years they still pass all military atmospheric exposure. tests. Forms that oxidize are usually . painted with protective epoxies, or plated with copper, nickel and cadmium to minimize oxidation. However, SOPS for demil must be prepared for worst cases, such as oxidized surf aces, etc. Comprehensive literature is available on the corrosion of uranium in various conditions and media.28 As each DU compartment is opened, a scanner should be used to detect an ' inordinate amount of radiation. The munition parts that do not contain DU- should be wiped with a smear sampler or scanned to detect uranium oxide accumulation and assure their inactivity before they are packaged as non radioactive parts. , i 3. Chemical toxicity from internal exposure, especially to the kidneys, is . a serious concern for those who work much with uranium, which is one of the poisonous heavy metals along with lead, arsenic, mercury, etc. DU from internal exposure is expelled only slowly, to further complicate the risk. A standard limit of 1 mg of uranium in the average kidney is equivalent to 3 ug per gram of kidney tissue, and to 0.2 mg/m3 in worker air." P 2-25te *-** The following chart puts this information into loading factors by body weight." ***** Class D represents the most soluble. uranium compounds which are excreted in the order of days, whereas most common uranium' types are excreted in several weeks.

Effect Uranium concentration Class D loading ecuivalent

No effect 0.04 mg/kg body weight 5.9 mg/kg body weight Maximal non-lethal 0.08 mg/kg body weight 11.0 mg/kg body weight LDoo 2.0 mg/kg body weight 294 mg/kg body weight

In most but not all conditions to be encountered, toxicity of internal uranium is more hazardous than its internal radiation danger." **-** Symptoms of severe uranium poisoning are: Lacrimation, conjunctivitis; - | short breath, coughing, nausea, vomiting; dermatitis, skin burns; casts in

, urine, high blood urea nitrogen, lymphatic cancer.82

4. Pyrophoric danger, and fire orecautions. Uranium metal is pyrophoric as thin or finely divided forms in air. This is a serious potential danger to those who work with DU. The pyrophoricity of uranium is of little concern with bulk items, which will sustain combustion only above about 500 *C, but is a danger in cases of* air exposure of mill shavings or powder with their high surface area. Machine turnings can have hundreds of square meters of surface area per kilogram, and can oxidize more rapidly than the heat can be dissipated, leading to ignition. Grinding sludge is even more dangerous. The danger of such a fire is many fold. It is extremely hot

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and not easily extinguished, which poses the threat of starting on fire anything else nearby that is combustible. The fumes contain much finely divided uranium oxide which is initially suspended in the air, with the associated risks described in 2 and 3. above. In the TEAD project no milling or grinding of DU will be allowed, except as described under MACHINE REQUIREMENTS. Uranium is pyrophoric only when finely divided in air. During milling (grinding, cutting', turning, etc.) of uranium met, , this potential risk is easily addressed by the une of aqueous cutting fluid. The milling residue is simply kept wet during operations, and stored under water thereafter to - prevent it from bursting into flame. Grinding sludge may have high enough surface area to react under water, and may have to be kept in a special' oil, mixed with sand for insulation, or cast in concrete for shipment.* Fires should not be doused with water, because burning uranium is so hot it reacts with water to form hydrogen gas, greatly enhancing the danger. The most recommended fire treatment is the use of an extinguisher that utilizes a dry chemical powder, such as MET-L-X. This is a mixture of sodium *8-** chloride and potassium carbonate.8 8 Neither water spray, carbon dioxide, nor halon extinguishers are effective against uranium fires. Halon may cause an explosion, and can produce very toxic fumes. Uranium fires can be smothered by total submersion under water, however, some hydrogen and oxygen gases will be produced by reaction with the water for a few seconds until the fire is out. Therefore, this method should not be attempted if the water available .for submersion is not plentiful, because the formation of these gases increases the fire and explosion hazard.

MONITORING METHODS, EXPOSURE LIMITS, SPECIAL PRECAUTIONS

Personal dosimeters. The most important radiation monitors for persons who work on demilitarization of DU munitions are the personal dosimeters, or body badges. These should be worn by personnel at all times when on duty, and should be analyzed monthly. The dosimeter should be capable of monitoring the exposure level of beta and gamma radiation. AMC is now recommending dosimeters or record keeping of the total life-time dose for each worker. Personal dosimeters for this purpose are available within the Army system from Lexington, KY, where the U.S. Army Ionizing Radiation Dosi:netry Center is located. The Dosimetry Center can provide the badges, the analytical service to assay the badges and report the exposure accumulation for each worker. The center is mission funded for personnel dosimetry. TEAD requests should be made through the TEAD Safety Office. See Appendix references for general laboratory services.

Exit tester for hands and feet. Workers in the restricted area wear shoe > covers that will not be taken out. Any time a worker must exit the | . restricted area the worker must remove shoe coverings (and gloves if any) at a designated place by the exit, place hands and feet on an exit testor for a few seconds until the machine signals hands and feet are free of radioactivity, and then exit immediately without turning back to the work area.

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Measurement of internal exposure. Because suspended particulate in air is the most immediate concern as a direct route for introduction of radioactive naterial into the bodies of DU workers, this subject warrants special attention. Outlines of industrial hygiene requirements and supporting information are available,8.88 in addition to the regulations.** DU workers in DOE are ordinarily scheduled for a lung count or whole body count every 6 months. But the only device that could be located within 200 - miles of TEAD for measurement of lung or whole body counts was recently dismantled (at the University of Utah). For this reason, the AMC Health Physics office (Pat Elker, AV 284-5476) has suggested an alternative procedure: Personal dosimeters and air monitoring samples will be followed closely and logged carefully. Background levels should first be established with the same work room air monitoring samplers, for comparison with the readings taken when work is being done with DU devices. No measurement of internal exposure need be made for low level exposure, If the personal dosimeters or air monitors show an increase in activity more than 257. of the maximum permissible count (MCP) in the air, the workers should have urine samples analyzed. If measurement of internal exposure is later considered for the workers then it could be done by analysis feces for a week, or by measurement of gamma radiation in a lung counter. AEHA can do fecal analyses (bioassays), see Appendix for addresses.

Fecal assays can also be done by the University of Utah Environmental Radiation Laboratory, run by Dr. Ed Wrenn, te3ephone 801-581-5917. DPG is capable of such analyses, but is not currently set up for it. Dugway is currently set up for beta counting of samples with the standard Army AN/PDR27J counter, which would allow an indirect calculation of the uranium by the known 2.29 Mev beta band of the protactinium daughter. It is not known from this study whether there are other qualified labs in the TEAD area.

For direct lung counting, should an emergency arise that warrants it, personnel could be sent to a clinic at Denver, Idaho Falls, Las Vegas or California, or else a contract could be let to one of these clinics to bring a unit to the Salt Lake area for the measurements. That procedure will take up to an hour in order to get the accuracy necessary for worker protection. Both methods are expensive, and a cost study or competitive bidding would be necessary to determine the most economical way. Another possibility is to have the AEHA contact given above make arrangements with the DOE for Army personnel to go to a DOE f acility to have the whole body or lung counts made.

Air monitors. Input and exhaust air monitoring is discussed in the section on WORX AREAS. Monitoring of surf ace contamination. Surface contamination is monitored by smear samples, also known as wipe samples, which are discussed in the section on WORK AREAS.

Special clothing. Protective clothing is worn in the restricted work area. Shoe coverings are important to prevent dust or grit from being tracked outside that area, and will be removed upon exiting the restricted area.

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~ '

: . - t

Special~ clothing may ~ be considered for the outer work room also, but ordinarily this is not necessary. Special clothing will not be ' worn upon exiting the outer work room into the outdoors.

Respirators. . Use of respirators is regulated in 10 CFR 20.103.88 - For demil procedures with DU devices, respirators will- not be considered : necessary if proper air flow, air pressure controls,. strict work routines and protocol are maintained, as outlined in _the other sections. Exposure limits. Personal monitors worn by workers in 'the restricted areas are to be analyzed periodically to determine the accumulative doses. Permissible doses are- specified in reference : 23, part 20.101 to 20.108. _ An - individual cannot be allowed to receive more exposure than indicated |below,- with some exceptions described in the reference.

Permissible Dose, rems per Calendar Quarter

1.25 Whole-body;. head and' trunk; lens of eyes; active. blood-forming organs;-gonads

18,75 Hands & forearms; feet & ankles

7.5 Skin of whole.' body

SOURCES OF INFORMATION FOR COMPILATION OF SOP'S The information outlined in this report and the references ' cited, together with the total description of military devices involved, will provide sufficient information for compilation of SOPS for demil of those devices.- The most important references for this purpose 'in _ order of usefulness are: 4, 22, 3, 2, IS, 17, 18. Reference 4,' the DARCOM handbook of 1978 'is now. (1988) being updated and1 rewritten by Battelle NW Laboratory for .U.S. - Army - Materiel Command (AMC, which DARCOM became since. the.1978 ' edition), by_ a contract through.LABCOM. The current DU POC at the AMC Safety 0ffice is Health Physicist Ralph Cardenuto, AV-284-9340.

23

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t, _ _ m * -__ ,- w s.EM . , ,.

* ' * ,. ,.

. - ,

APPENDIX

SHIPPING OF DU PARTS AND SCRAP DU, natural uranium and thorium are * low specific activity * (LSA) materials which benefit from liberal shipping rules. DOT regulations in 49 CFR 173,2* define LSA materials as a class to include uranium and thorium metals, cres and concentrates; other materials must have activity below certain limits to qualify as LSA.

Typical packaging ***''****'2*'2''2* consists of a 30-gallon steel drum inside of a 55-gallon drum. Large pieces. of scrap are put in without additives. Non-pyrophoric chips are commonly mixed with vermiculite or sand. If the radioactivity level at the outer surface of the package can be kept below 0.5 mr/hr it can go as limited quantity radioactivity material under 49 CFR 173.421 or 424.2*'2" Millings or fine particulate

. should preferably be oxidized completely before shipment to avoid special conditions for pyrophoric material; as oxide it can be shipped by the liberal rules for ores. Otherwise it can be cast into concrete blocks for shipment in the double drums as * Uranium, Pyrophoric,* according to 49 CFR 172.101 b12 and b13.

Shipping papers are covered in 49 CFR 172.202 and .203d. Summaries on labeling, packaging and shipping are available* 2*'1'*2**** in more concise outline form than the DOT regulations themselves.2" The most pertinent consideration for DU containers, in whatever form, is that they be able to withstand a prescribed amount of mechanical shock and exposure to fire without releasing uranium. General regulations for radioactive materials are also available in a special publication.**

The TEAD RPO reports that AMCCOM, the originator of references 17 and 18 has established contracts for the disposal of radioactive waste. TEAD will follow AMCCOM instructions on allowable containers and how to pack, mark and label the material. Properly packaged and labeled DU metal and radioactive waste from TEAD operations will be inspected by the TEAD RPO and shipped with his approval and guidance. '

ADDRESSES FOR LABORATORY SERVICES

Army centers: Chief US Army Ionizing Radiation Dosimetry Center ATTN: AMXTM-SR-DC (Ed Abney, AV-745-3249)

Lexington, KY 40511-5102 <

CO, US Army Environmental Hygiene Agency - ATTN: HSHB-ML-R (Ron Swatski, AV 584-3619) Aberdeen Proving Ground, MD 21010

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._ ..

-- . , -.

*

? . .

Commercial centers: University of Utah Environmental Radiation Laboratory ATTN: Dr. Ed Wrenn (tel 801-581-5017) Salt Lake City, Utah

R. S. Landauer Jr and Co. Glenwood, IL 00425-1580 (tel 312-755-7000)

Eberline Dosimetry Service Santa Fe, NM 87501 (tel 505-471-3232)

Radiation Detection Corp Sunnyvale, CA 94080

CHEMICAL SYMBOLS

Chemical symbols use standard one- or two-letter abbreviations for each chemical element according to world wide conventions of the International Union of Pure and Applied Chemistry (IUPAC) and other universally accepted - organizations. Some of the symbols reflect the Latin names of the elements rather than their English names, and so are also accompanied by spelled-out English names in this report. The four corners of a symbol, the preceding and following subscript and superscript positions, are used for standard types of information about the element in particular discussions. The mass number goes at the upper left, as with "*U, read mass 238 uranium or uranium-238, the main isotope in natural uranium. The atomic. number goes at the lower lef t, as ' with .aU. All isotopes of the same element have the same atomic number, representing the positive charge of the nucleus of that element. Atomic number is of ten left off, the symbol being sufficient information to identify it. The ionic state goes to the upper right, as with Au"* for the auric ion of' gold with a positive three charge. The number of atoms bonded together (per molecule or ion) goes to the lower right as with UFe for uranium

hexafluoride. .

THE TWO URANIUM DECAY SERIES

The expressions (4n + 2) and (4n + 3) with n = integers are used to describe the two uranium decay chains or series. All nuclides in the two series have mass numbers given by these expressions. The mass number is the integer approximately equal to the mass of the nuclide. Nuclides in the same series differ from each other in mass number by some multiple of 4 because radiation of an alpha particle, or helium nucleus *He** 1 eaves the nuclide that radiated it with a loss of 4 mass units. Gamma radiation and less of an electron or beta particle seldom cause a mass loss of more than ' a few thousandths of an amu. Rest mass of the electron is only 1/1823 amu. Most gamma radiation from DU is between 0.03 and 1.8 MeV or about 0.00003 to 0.002 amu equivalent (1 MeV = 0.0010737 amu). Thus the mass number of a nuclida differs from the mass number of the parent in that chain by a multiple of 4. Mass numbers in the ***U series all fit the expression (4n i + 2), and those in the ***U series all fit (4n + 3). '

25

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I

, __- _

M ' . * . .

* ? 4

.

***U Series (4n + 2) ***U Series (4n + 3)

Symbol Name Half-life Symbol Name Half-life

***U uranium-238 4.51E9 yr ***U uranium-235 7.1E8 yr : ***Th thorium-234 24.10 day ***Th thorium-231 25.52 hr : ***=Pa protactinium-234m 1.175 min ***Pa protactinium-231 3.25E4 yr : \ | | ***Pa protactinium-234 6.75 hr / **'Ac actinium-227 21.6 yr : / \ ***U uranium-234 2.47E5 yr ***Th \ thorium-227 18.2 day : ***Fr francium-223 22 min ***Th thorium-230 8.0E4 yr : / r | | / ***Ra radium-226 1602 yr ***Ra radium-223 11.435 day : asaRn radon-222 3.8229 day ***Rn radon-219 4.00 -sec ! ! ***Po polonium-218 3.05 min ***Po polonium-215 1.78 msec : \ | \ ***Pb \ lead-214 26.8 min ***Pb \ lead-211 30.1 min ' : ***At astatine-218 1.5-2.0 sec : 82*At astatine-215 ca 0.1 msec

: / | / : : / / ***Di bismuth-214 19.7 min ***Bi bismuth-211 2.16 min : \ 1, \ ***Po \ polonium-214 164 usec ***Po \ polonium-211 0.52 sec : ** T1 thallium-210 1.32 min **'T1 thallium-207 4.79 min / ! / / | / ***Pb lead-210 20.4 yr **'Pb lead-207 stable : 82*Bi bismuth-210 5.013 day : \ ***Po \ polonium-210 138.40 day ***T1 thallium-200 4.19 min : /

/ < ' ***Pb lead-206 stable

i

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1

a | . .

. . , s

* . . , .

ABBREVIATIONS

ACGIH American Conf erence of Government Industrial Hygienists AED Ammunition Equipment Directorate at TEAD Ag silver (argentum)

AMC U.S. Army Material Command (f ormerly DARCOM) _ AMCCOM U.S. Army Armament, Munitions and Chemical Command amu atomic mass unit (931.35885 MeV energy equivalent) AR Army Regulations ASM American Society for Metals Au gold (aurum) ave average C degrees centigrade or Celsius CFR Code of Federal Regulations Ci curio = 37 billion atom dps***'****' P''' 2 cm3 cubic centimeter Cu copper (cuprum) D38 depleted uranium DARCOM U.S. Army Materiel Development and Readiness Command (now AMC) demil demilitarization D0D Department of Defense DOE Department of Energy dps disintegrations per second DU depleted uranium E powers of 10 (1.4E5 = 140,000; 1.4E-5 = 0.000014) ed. editor, edition esu elec$rostatic unit (of charge, etc.) F fluorine Fe iron (f errum) g gram GPa gigapascal, 1,000,000,000 pascal (pressure - unit) = 145,000 psi HDBK handbook HB Brinell hardness He helium HV Vickers hardness HK Knoop hardness HEB, HRC Bockwell hardness, scale B, scale C ICRP International Commission on Radiological Protection IUPAC International Union of Pure and Applied Chemistry kev thousand electron volts (energy unit = 1.0E-9 erg) LSA Low Specific Activity; LSA materials have liberal DOT rules; uranium, thorium & their cres are LSA; other items ' qualify by a low level of radioactivity (see ref 16, 23 part 173.389) . MeV million. electron volts (energy unit = 1.6E-6 erg) Mil specs military specifications min minute - mm millimeter Mo molybdenum Modul.Elart. Modulus of Elasticity MPa megapascal = 1,000,000 pascal (pressure unit) = 145.04 psi mB/hr milli-Roentgen per hour msee millisecond

27

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, * .

. - . ,

usec microsecond Nb niobium NCRP National Council on Radiation Protection and Measurements Ni nickel No. number ^

n9.m nano-ohm meter (resistivity unit) _ NRC Nuclear Regulatory Commission Pa protactinium a**=Pa metastable protactinium-234 (a high energy. isotope) Pb lead (plumbum) PRON Procurement Request Order Number (project budget reference) psi pound force per square inch (pressure unit) Pt platinium R roentgen: amount of gamma or X radiation that ionizes air to the extent of 1 esu of positive or negative charge per 0.001293 gram of air; this is 1 ml of air at 0 *C and 1-atm; 1 esu/ml also = 2.58E-4 coulomb /kg = 87 erg / gram of air. rad radiation absorbed dose of 100 ergs absorbed / gram of. tissue, rem roentgen equivalent man, dose of ionizing radiation that gives a biological effect equivalent to that of 1 R. gamma ray; this is 0.1 rad from high energy neutrons or protons.* * 2* *' **"' 8* See ref erence 23 f or chart of rem equivalent by flux density. Re rhenium RPO Radiation Protection Officer (ref 4, p 1-23). sec second s/lb dollars per pound STEL short term exposure limit (usually for 15 minutes) TEAD Tooele Army Depot, Utah Temp. temperature Th thorium Ti titanium U uranium W tungsten (wolf ram) yr year Zr zirconium '

RL TRENCES

1. Demilitarization of Depleted Uranium Ammunition - Concept, TEAD PRON M18MQ307, Project No. T-2-88,

2. U.S. Nuclear Regulatory Commission Materials License No. SUC-1391 (Docket reference 040-08779), 3rd amendment, Tooele Army Depot Utah, for uses at Tooele and at Pueblo Depot Activity, Colorado, 26 Apr 1988.

3. Health Physics Manual of Good Practices for Uranium Facilities,, Dept. of Energy publication EGG-2530 UC-41, B. L. Rich, et al, Idaho National Engineering Laboratory. Idaho Falls, ID 83415, June 1988.

i

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. . , < e ' ,

4. Safety Procedures for Processing Depleted Uranium, DARCOM HDBK 385-1.1-78 Army Material Development & Readiness Command, Alexandria VA, Aug 1978, now being rewritten by Battelle, NW for Army Materiel Command (AMC).

5. Encyclopedia of Explosives and Related Items, Seymour E Kaye, et al, U.S. Army Armament Research and Development Command, Large Caliber Weapon Systems Laboratory Dover, N.J., volume 10,1983, U85-95.

6. Metals Handbook, 9th ed., ASM Handbook Committee. American Society for Metals, Metals Park, Ohio 44073, 1978; a) DU: volume 2 page 821, volume 3 pages 773-780; b) tungsten: volume 2 pages 325-32, 348-9; c) other articles all volumes.

7. Encyclopedia of Explosives and Related Items, see ref #5, volume 8, 1978, P503-511.

8. The Merck Index,10th ed., M. Windholz et al ed., Merck & Co., Inc., Rahway, N.J.,1983.

9. The Condensed Chemical Dictionary,10th ed., G. G. Hawley, Van Nostrand Reinhold, N.Y.,1981.

10. Grant & Hackh's Chemical Dictionary, 5th ed., R. Grant & C. Grant, McGraw-Hill, N.Y.,1987.

11. Lange's Handbook of Chemistry,12th ed., J. Dean, McGraw-Hill, NY,1979.

12. Handbook of Chemistry and Physics, 59th ed., CRC Press Inc., West Palm Beach, Florida,1978.

13. Compilations by suppliers.

14. Metal Statistics 1987, American Metals Market, Fairchild N.Y.,1988,

15. Corrosion and Its Control, Physical Metallurgy of Uranium A11 ors, Proc. Third Army Materials Technology Conference, Vail CO,1974, 2nd ed., J. J. Burke et al, ed., Metals and Ceramics Information Ctr, Columbus OH and Brooke Hill Publishing Co Chestnut Hill MA,1970, p 773-1002.

16. *A Review of The DOT Regulations for Transportation of Radioactive Materials,' U.S. DOT, Hazardous Materials Office; U.S. Government Printing Office, Washington, D.C. 20402, Summer -1983.

17. Handbook for Disposal of Unwanted Radioactive Material AMCCOM Pamphlet 385-1, U.S. Army Armament, Munitions and Chemical Command, Rock Island, IL 61299-6000, June 1987. I 18. Handbook for Disposal of Radioactive Waste in Accordance with U.S. Army Guidelines, AMCCOM Handbook SF-1, U.S. Army Armament, Munitions and

Chemical Command, Rock Island, IL 01299, June 1983, , I

t 29

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19. Title 49 Code of Federal Regulations, Department of Transportation, especially parts 172 and 173, U.S. Government- Printing Office, Washington, D.C. 20402, October 1988.

20. Design and ConAtruction of High-Efficiency Air Filtration Systems for Nuclear Applications, ORNL-TM-2300, C. A. Burchsted & A. B. Fuller, Oak Ridge National Laboratory, Oak Ridge TN, September 1968.

21. U.S. Nuclear Regulatory Commission Materials License No. SUC-1394 (Docket 040-8789), Savanna Army Depot Activity IL 61074, 21 May 1986.

22. Standing Operating Procedure, No. SV-B000-J-036, Change No.1, Savanna Army Depot Activity, Savanna, IL 71074, September 1988.

23. Title 10 U.S. Code of Federal Regulations, especially parts 19, 20, 21, 40 & 71, U.S. Govt Printing Office, Washington, D.C. 20402, January 1988.

24. Military manuals: WS 10765B Oct 1979, TM 43-0001-28, TB 43-0116 App B, have details on some pro.iectiles of concern for the TEAD license.

25. Limits for Intakes of Radionuclides by Workers, ICRP-30, Part 1 Supplement, Pergamon Press, N.Y., Apr 1980.

26. Regulations for the Safe Transportation of Radioactive Materials, as amended, Safety Series #6,1973 Revised Edition - International Atomic Energy Agency (IAEA), Ylenna, Austria. Available from UNIPUB,1180 Avenue of the Americas, NY,10038. ,

27. Occupational Safety and Health Administration (OSHA) General Industry Standards for Safety and Health, OSHA 2206, 29 CFR 1910, U.S. Dept of Labor, U.S. Govt Printing Office, Wash D.C. 20402, June,1981, p 631-636. See also 54 FR 2332 (January 1989 Federal _ Register).

28. Threshold Limit Values and Biological Exposure Indices (TLV's), American Conference of Governmental Industrial Hygienists (ACGIH), Cincinnati, Ohio, 198d-1987.

79. Basic Radiation Protection Criteria, NCRP Report No. 39, National Council on Radiation Protection, 7910 Woodmont Ave., Suite 1016, Bethesda, MD - 20814,15 Jan 1971.

30. Maximum Permissible Body Burdens and Maximum Permissible Concentrations . of Radionuclides in Air and in Water for Occupational Exposure, Handbook - 69, National Bureau of Standards, Gaithersburg, MD, Jun 1959, Aug 1963; also available as NCRP Report No. 22 at address given in reference 29.

31. Handbook of Toxic and Hazardous Chemicals and Carcinogens,- Marshall. Sittig, Noyes Publications, Park Ridge, NJ,1985, p 910.

30 .

6

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NRC MATERIALS LICENSE #SUB-1391, suplement 2

STATISTICAL SAMPLING PROCEDURE FOR SMEAR TEST FOR DU CONTAMINATION 1. The statistical sampling procedure should not be used for radiation surveys of material for release for unconditional use, nor for routine surveys of personnel, lunch rooms, break rooms, or personal property. The procedure may be useful in determining isotopic composition of radioactive contamination in an area or on equipment. 2. The minimum number of smears to be taken should be based on HIL-STD- 1050, " Sampling Procedures and Tables for Inspection by Attributes." The following sampling parameters should be used for determining compliance with average and peak limits of contamination (Chapter 3, Section 3.16): (a) General Inspection Level I (see Table H.1 and Table I, MIL-STD-1050). (b) single sampling Table II-A, MIL-STD-105D)- Addplan three for normal more toinspection indicate sample(see Table size. H.2 and (c) Acceptable Quality Level (AQL) 6.5. 2.1 At no time should the minimum sample be fewer than five smears. For determining the number of smears, the lot size is defined as the total area in square feet (see Table H.1). The sample size is a minimum. Judgment by the RPO should dictate whether additional smears should be taken of a given area. 2.2 The accept / reject criterion specifies the number of smears that can peak above the average limit specified in Table 3.16. Peak contamination levels are allowed up to five times the average limit. All other smears must be within the average limits specified in Table 3.16. 2.3 Example: (a) floor area: 250 ft2 (Lot Size 151 to 280 per Table H.1) (b) General Inspection Level I, Lot Size Code-E (c) sample size: 13 + 3 = 16 smears . (d) AQL: accept 2, reject 3 (e) Summary: Sixteen smears are taken. Two smears can exceed the average limit in Table 3.16 by up to five times. Three smears above the limit is cause for decontamination and resurvey. Another cause for decontamination and resurvey is if the average of all smears does not fall within the average limit. ) '2.4 To increase the number of smears, the next sample size code letter can ! be used. This may allow for an increase in the number of smears permitted , above the average limit in Table 3.16. In the case of the example above, the 1 next Lot Size Code is F, which calls for a sample size of 20. Add 3 for a j total of 23 smears (see Table H.2). The accept / reject criterion for peak ; values would now be accept 3, reject 4. '

N.1

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.

TABLE H.1. Sample Size Code Letters

, sc us.1 a.. c si.. lo.l. G..,nl s..cuu.. lo l. Les .e beach slas

5-8 52 13 5e t i 18 Ill

2 s. 4 A A A A A A Il 9 s. 15 A A A A A Il C 16 s. 25 A A II 18 il C D

26 s. 50 A D D C C D E * Si e. 90 B D C C C E F 98 e. ISO B B C D ll F G f . . '- ro 151 s. 280 R C D E E G ll 2el s. 500 B C D E F Il 3 Sol s. 8200 C C E F G 1 N

3 1201 s. 3200 C 16 E G la E I. 3?ol s. 10000 C la F G 1 L si 10008 s. 35000 C 11 F || K M N

35004 s. 150000 f) E G 3 8. N 15 150008 s. 500000 D E G I N l' y 500004 ..J evu D E u il N N y 14 h

A - _ _ . . _ - . . _ _ _ . ______.__m______m______, _ _ _ * _ ' _ _ _ .

_. . _ - . _ .. _

._ _ _ . e 4 . 0 S . 0 R 3 4 ._. 0 c 0 4 s 1 3 4 A _ 2 9 5 O 2 3 4 6 S A E c 1 0 4 s 2 3 4 A _ 5 2 1 S 0 1 g 0 N 2 3 4 4 c o 1 0 4 ; A t 2 3 4 _ e 1 S 2 1 S 0 1 I 2 3 4 g _ 5 R 2 c 0 4 1 0 4 , ' _ 1 1 3 A 2 4 _ 2 S 1 5 1 g . 0 1 1 2 3 5 N 1 1 c i o 4 0 j l_ A t 1 2 3 e e 8 1 5 2 0 R 1 1 2 , 0 . 1 c S 7 0 o 1 j ) A 1 t 2 e e 4 6 8 8 5 2 1 1 g l 5 R 2 6 . c 3 5 7 o 1 ; b t a A 14 2 e 3 4 6 0 1 5 2 T g . 0 R 1 1 2 i 4 c 2 3 5 7 0 4 1 a r A 1 1 2 e e 2 3 4 6 e 1 5 2 , _ t 5 R 1 1 2 2 5 j ._ s c 1 2 3 F o 4 1 a a t 1 2 H e 2 3 4 S 8 1 5 2 g ( S R 1 1 2 I c %i2 3 S 7 0 4 1 s n A 1 1 2 e 2 3 4 8 S 9 5 2 g o 1 1 i o R 2 t t c 1 2 3 S F 0 4 1 s c A 1 1 2 1 ) e 1 2 3 4 e e 5 2 e 1 1 g p n 5 R 2 6 c 0 gk 1 2 3 S 7 0 4 1 j s .o 1 1 2 n A ap t 2 3 4 6 8 1 5 2 I 0 N 1 1 2 $ m 4 c 2 3 S F o 4 1 s _ l la A h0 $$1 t 1 2 a m t 4 3 5 2 r 2 3 S e g _ o 5 & 1 1 2 m n 2 c ( O 2 3 S 7 0 4 1 s _ r A 4$1 1 1 o 4 2 % e v 1 2 3 4 6 4 l 5 2 N S N i 1 2 e S l c 1 1 m A O 4$ 2 3 5 7 o 4 1 r iy t 1 2 o h a N t 3 4 6 8 1 5 2 f P . L o 1 1 2 4 ( t c pk2 A 9 0 1 2 3 S 7 0 4 1 s e 1 1 2 =. lb , n y t 3 4 4 4 1 5 2 a S N al a tp S 1 1 2 l c gy21 7 1 e O A 9 0 2 3 S 0 4 P c 1 1 2 . c e A 0 r t 2 3 4 8 S t 5 g 4 R i 1 c n 0 9 0 pk 1 2 3 5 F o 4 A t 1 i l S N r t 2 3 4 C 8 1 . p 2 1 o c p 7 c 0 A 9 0 3 S 0 m $i2 1 a e s 1 3 4 6 0 S s R r . c p2t e O A 9 0 2 3 5 7 l e 0 r t 2 3 4 6 g 1 R . c c 9 pS 1 2 3 5 . - n A 0 .e i . S 5 1 2 3 4 6 N r . 0 c . 0 A 9 0 4 $1 2 3 m . 0 1 2 3 ts .- 2 4 N r 0 1 c 3 0 2 1 C A 4k1 e 5 1 2 E 2 R r . L 0 c 0 pk 1 B 0 A 9 - 0 . e .e A S t . . T t R r . _ 0 c . ., r 9 0 e . 0 A r a m _ 0 t .o ,R F mmbu 0 c m m n mu 0 A 9 0 . ce n _ t n n e l a o npe 2 3 S 8 3 0 2 O 0 S 0 5 0 0 0 0 tp t 1 1 c e 2 3 S 8 2 0 0 0 5 0 ma 1 2 e e aS 2 3 5 4 0 . c } s 1 2 a. . c e e u lp e e , u. - A. R. c .e _ mse o o A 8 C D E F G H J K L M N P O R c e aS CL A R _ S + + _ _ ._ _ _ ._

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_ a . . NRCMATERIALS LICENSE'#SUC-1391, suptement.3- . DU Penetrator Ammunition Radiation Measurements Program 803L' (October 1984)

Site Ammunition Studied

Sierra Army Depot GAU-8 Milan Army Depot M833 Dahlgren Naval Station Phalanx

Purpose: To check portable instrument responses to typical handling and storage configurations.

.

Portatti. Instrum.nt M.. tut.m.nt Points on Shippmg Container d fA s Y_ ' ' A ' . ' . . . .:I,:".. ,, , ." . . . . i'. .:. ,.,. g,..h a : ...... - ; '' ':. **' . . :. .1 1 ~c A ' ' ' ) , )y r' '& 'l >; . . ,, .: =' L . ; s. ., ,, : - s . . . .: .: .. .. . 3...... , * 'a .o . .j ,, ; .:, , . .

, J . 'n . . , ! ,, g. ; ! ,. . ,,. >[. ' " . . . ,, ! * , . . . , ! . , y ) A >,!. '". , ' .. *a...., i t. . . .

, . . . . . " . . . . , , :': B "'" - (4,,. ,":-|,;.g3g: | : ev \~ d . , ,

1 . ..

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~ ' Instrument Description

Calibration Calibration __ Instrument Detect.or__ Source Laboratory

Ludlum Model Scintillation Nat U -PNL 12-S

Eberline RO3-B Ion-Chamber Nat U PNL ,

Eberline E-140 Thin-Window Nat U PNL ; GM ,

Victoreen Compensated "Co Rock Thyac III GM Island Arsenal

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~ - - . GAU-8 In Storage (CNU-332) i

I 12-S R O3-B Thyac III E-140 Position (mR/hr) (mR/hr) (cpm) (mR/hr) |

Surface 2.7 1.4*- 1.4 * '4500 1 One Foot 2.4 1.1 0.8 3500

One Meter 2.0 1.0 0.7 2500

Between Pallets 1.7 0.9 0.5 2500

i Maximum Readings: Top !

!

4

GAU-8 In Storage (CNU-309)

I 12-S RO3-B Thyac III- E-140 Position (mR/hr) (mR/hr)_ (mR/hr) (cpm)

Surface 3.0 2.0 1.5 6500 .

One Foot 2.7 1.4 0.9 ' 4000 i

One Meter 1.8 0.7 0.5 2000 i

Between Pallets 3.0 1.3 - 1.2 5000 't

i Maximum Readings: Side i j

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' ~ ' GAU-8 In Storage (M548) ,

, 12-S RO3-B Thyac III E-140 Position (mR/hr) (mR/hr) (mR/hr) (cpm)

Surface 3.0 1.8 1.25 6000

One Foot 2.3 1.4 0.8 3000

One Meter 1.7 0.8 0.5 :2500

i Between Pallets 2.3 1.3 0.8 4500

Maximum Readings: End

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GAU-8 On Inspection Line |

12-S R O3-B Thyac III E-140 Pasilion (mR/hr) (mR/hr) , (mR/hr) (cpm) ;

Surface 1.3 0.6 0.8 9000

Operator 0.1 0.2 0.6 3500

, Isolated 0.7 lYQ 1.0 lVJQ 1.3 10,000 Round E - 0.4 E 0.4

, Exposed 0.4 lLQ '5.0 lYO 10.0 55,000 Penetrator E 0.5 E 0.4 U

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. M-774 In Storage (4704 Round Load)

12-S RO3-B Thyac M E-140 Position (mR/hr) (mR/hr) (mR/hr) (cpm)

Surface 1.0 0.4 0.4 1500

One Foot 0.6 0.2 0.2 600

One Meter 0.4 0.1 0.1 200 Igloos Aisle: 240 R/hr Background at 50': 13 uR/hr

i

M-833 In Storage

12-S RO3-B Thyac m E-140 M on (mR/hr) (mR/hr) (mR/hr) (cpm)

Surface 1.8 1.0 1.0- 3000

One Foot 1.3 0.8 0.6 2000-

One Meter 1.1 0.6 0.4 1500 , Center Aisle: 180 g R/hr Background at 50': 13 R/hr

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' ~ Projectiles in Storage -

12-S R O3-B Thyac III E-140 M333 (mR/hr) (mR/hr) (mR/hr) (com)- -

Surface > 3.0* 2.4 1.7 7000 ' One Foot > 3.0* 1.8 1.2 5500 ' One Meter 2.8 1.2 0.8 4000

M774

Surface > 3.0* 2.0 EQ4.0 15,000 | EC1.4 '

One Foot > 3.0 * 1.5 1.2 5000 One Meter 2.6 1.0. 0.6 3500 '

Igloos aisle: 75 R/hr Background at 50' 11 R/hr ' *Offscale Reading

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' : Phalanx in Storage :

.

Earallel Pallets Y

' 12-S RO3-B Thyac III E-140 Position (mR/hr) (mR/hr) (mR/hr) (com)

Surface 1.4 1.2 0.9 Failed , One Foot 0.8 0.5 0.4 a

One Meter 0.3 0.2 0.1 l

Between Pallets 1.8 1.4 0.9 |

Background on Dock: 12 pR/hr | ! o

-, - -

1 . .- 4

~ ' Phalanx in Storage

Single Package

12-S R O3-B Thyac III '' Position (mR/hr) QuR/hr) (mR/hr)

Surface 1.2 1.0 lV_Q. 2.5 E 0.8

One Foot 0.3 0.2 lYQ 0.6 E 0.2 Single Round (Unpackaged) '

Surface 0.3 lVD 0.5 1Y O 0.5 E 0.3 E 0.3 Background on Dock: 12 u R/hr

' Phalanx in Storage

12-S RO3-B Thyac III - Position (mR/hr) (mR/hr) (mR/hr) '

Surface 1.5 1.2- 0.9.

One Foot 0.8 0.7 0.5

One Meter 0.3 0.1 0.1

Background on Dock: 12 u R/hr

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NRC Materials License #SUC-1391, supplement 4

M86 Antipersonnel Mine (PDM & ADAM) Demilitarization & Treatability

The purpose of this testing is to identify the quantity of DU that would be separated from M86 antipersonnel mines upon heating and the quantities of DU available for distribution to the atmosphere or ground as an aerosol or oxidized powder. This testing must identify the health, safety and environmental effects of demilitarization so that demil procedures'may be developed. Plans for future demilitarization of new or currently fielded munitions have been increasingly important to the analysis of total life cycle costs and environmental effects of weapons production. In the case of the M86 mine, the use of depleted uranium in the form of uranyl acetylacetonate (UAA) in the molding compound presents the possibility of DU contamination during demil. Data from tests will be used to formulate policy and procedures for the demilitarization of M86 mines. { The whole test project will involve about 200 mines. Each mine contains 0.1 gram of DU with an activity of 0.036 uCi. Because the mine contains 206 grams of molding compound filler, the concentration of DU is 0.049%. The 200 mines to be tested contain a total of 20 grams of DU with a total activity of 7.2 uCi.

DU in the mines is in an insoluble form. Incineration will convert it to a partially soluble form. Incineration will give both flue emissions and solid ash. nearly all of the DU is expected to be in the ash, with a trace of it in the baghouse dust. One of the purposes of the test is to determine how much of the DU goes into the flue. Final emissions in the air will not contain a measurable amount of DU. Any resulting fraction of the low radiation strength of the feedstock will be difficult to detect against normal background radiation. Exploding of some mines is expected but will be avoided by optimizing furnace conditions to get total decomposition. Testing

protocols will include temperature ramping to determine the minimum | temperature and residence time required to decompose the explosive ' without exploding it and to identify an effective feed rate. ! | Background air sampling will be conducted prior to and.during the testing for DU contaminates. Samples of the solid or ash residues will be collected and analyzed to accurately identify the quantity and chemical form of the DU present. If sufficient particulate is recovered on the air sample filters, particle size and lung solubility testing will be initiated to help determine its inhalation hazard. Using measured stack emissions, ash residues and furnace wall wipe sampling; a mass balance for the DU will be determined if possible.

| The ARDEC safety office has requested an interpretation from the ! NRC on whether the waste product would come under their j - , 7-' ..

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jurisdiction. It is believed that the NRC will not regulate the waste unless the treatment process concentrates the DU above 0.05 percent. The air emissions from the furnace deactivation test will be compared to ACGIH threshold limit values and 10 CFR 20 radioactivity limits to identify any potential hazard to workers or to the public. Current airborne limits of 0.2 mg/m3 (insoluble

uranium) averaged over a 40 hour work week will provide some . perspective for the relative hazard of actual releases and of ! projected releases for the demiling of large numbers of mines. The ' solids will be analyzed to assure that the DU content is below regulatory limits for low level waste. Good health physics practices will be used for worker protection where workers could be exposed to airborne DU.

It is difficult to conceive of a situation where the public would. be subjected to any DU from this operation. However, with large batches of mines being demilled over a short period of time, an analysis showing the public impact may be required. After determining the amount, if any, of DU being released from the ' stack, doses can be calculated for downwind populations using the computer program DUDOSE, developed by Pacific Northwest Labs to estimate doses from fires involving DU. PNL's GENIE II computer code provides a more extensive pathway analysis should this be required.

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(LG S 11992 . . . , , . , . . _ _ . . . . . PDM / ADAM SYSTEM DESCRIPTION , %> My e ,n .m,+ c < :&,.$Q i sn <:.u ...... y myQgggt The M86 Pursuit Deterrent Munition (PDM) mine is a hand- ' emplaced version of the antipersonnel mine contained in the -y y 155-mm M692/M731 Area Denial Artillery Munition (ADAM) - ;; - system. Each Mine is shaped like a pie slice, 7.6cm high with a flat top and bottom and two flat sides forming a 72* . angle opposite a rounded side with a radius of about 6.3 cm. , Seven tripline sensors are molded into the edges of the mine, y four on top and three on the bottom, at about 45* angle with respect to the adjoining side surfaces. The PDM is different g j, from the ADAM because of the external arming mechanism is ' place cr top of the mine and is included in the 7.6cm height. The PC:' ;e shown below:

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U.S. Nuclear Regulatory 02tmission v - Region IV j'g ,gdk- Nuclear Materials Licensing Section ATIN: MP. Vivian Campbell #B 3892 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011

Reference: Renewal of U.S. Nuclear Regulatory 02mtission (NRC) license SUC 1391 issued to Tooele Army Depot, Tooele, Utah . Dear Ms. Cangbell: This note confirrns our telephone conversation of-this norning regarding the reference.d license.

The NRC license SUC-1391 is slated to expire on August 31, 1992. We had intended to have the renewal submitted to you by August 1, but Arnry staffing has not yet been completcd. Since you will accept the renewal packet anytime prior to August 31, we will be able to ccuplete our staffing procedures. The renewal packet will be subnitted to your office 'no later than August 31.

Thank you for your assistance in this rnatter. For further information, please contact me at (703) 274-9340. Sincerely, / 1 /V \,./dof /[)A 4 ' John G. Manfre ' Cilief, Health Physics, Safety office

Copies fu1T11shed: CCMWDER DESCCH, ATIN: AMSDS-D1-S TEAD, A'ITN: SDSTE-IR-S

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