alliant techsystems operation (atk), inc., license renewal ... · atk lake city facility...

ATK Armament Systems Small Caliber Systems P.O. Box 1000 Independence, MO 64051-1000

Proud Operator of the Lake City Army Ammunition Plant

www.atk.com

Alliant Techsystems (ATK) Operations IIc. Plant Lake City Army Ammunitiot

P.O. Box 1000 Independence, MO 64051 - April 28, 201 1

000

Materials Licensing Branch U. S. Nuclear Regulatory Commission, Region Ill 2443 Warrenville Road, Suite 21 0 Lisle, IL 60532-4352

Subject: License Renewal Request for License Number 24-24576-01

Dear Sir or Madam: We are requesting the following package be reviewed for the renewal of license number 24-24576-01 Amendment No. 24 and the following change be made to the license.

0 A corporate name change has occurred and I am requesting that the name on the license be changed to the following name stated below. This name change is not a transfer of the license, but just a physical name change for the company.

Alliant Techsystems (ATK) Operations Ilc. Lake City Army Ammunition Plant P.O. Box 1000 Independence, MO 64051 -1 000

If you have questions, please call me at (816) 796-7101 ex. 7571.

Sincerely,

Trent Trutzel Safety Engineer, RSO

Encl: 1. NRC Form 313 2. 3. 4. ATK Administrative Procedures 5. Training Documents 6. Radiation Inventory

NRC License Number 24-24576-01 Amendment No. 24 ATK Lake City Facility information

http://www.atk.com

JRC FORM 313 US. NUCLEAR REGULATORY COMMISSION I APPROVED BY OM6 NO. 3160-0120 EXPIRES 3\31/20

APPLICATION FOR MATERIALS LICENSE

3-2009) 0 CFR 30,32.33, 14. 35, 36, 39, and 40

or by infemet e-mail to infocolleas.resourc'eQnrc.gov. and to the besk Omcer, Office Information and Regulatory Affairs, NEOB-10202, (3150-0120), Office of Managemc and Budget, Washington, DC 20503. If a means used to impose an informati collection does not display a currently valid OMB control number, the NRC may I conduct or sponsor, and a person is not required to respond to, the informati collection.

Estimated burden per response to comply with this mandatory collection request: 1 I hours. Submittal of the aoplication is necessary to determine that the applicant

LPPLlCATlON FOR DISTRIBUTION OF EXEMPT PRODUCTS FILE APPLICATIONS WITH:

ualified and that adequak procedures exist to protect the public health and safe end comments re arding burden estimate to the Records and FOlAlPrivacy Servic

IT-5 F531. b S Nuclear Reaulaton Commission. Washinaton. DC 20555-001

IF YOU ARE LOCATED IN:

'LABAMA, CONNECnCUT, DELAWARE, DISTRICT OF COLUMBIA, FLORIDA, GEORGIA, .ENTUCKY, MAINE, MARYLAND, MASSACHUSETTS, NEW HAMPSHIRE, NEW JERSEY, IEW YORK, NORTH CAROLINA, PENNSYLVANIA, PUERTO RICO, RHODE ISLAND, SOUTH :AROLINA. TENNESSEE, VERMONT, VIRGINIA, VIRGIN ISLANDS, OR WESTVIRGINIA, END APPLICATIONS TO:

OFFICE OF FEDERAL 8 STATE MATERIALS AND ENVIRONMENTAL MANAGEMENT PROGRAMS DIVISION OF MATERIALS SAFETY AND STATE AGREEMENTS US. NUCLEAR REGULATORY COMMISSION WASHINGTON, CC 205554001

rLL OTHER PERSONS FILE APPLICATIONS AS FOLLOWS:

: YOU ARE LOCATED IN:

ALASKA, ARIZONA, ARKANSAS, CALIFORNIA, COLORADO, HAWAII, IDAHO, KANSAS, LOUISIANA, MISSISSIPPI, MONTANA, NEBRASKA. NEVADA, NEW MEXICO, NORTH DAKOTA, OKLAHOMA, OREGON, PACIFIC TRUST TERRITORIES, SOUTH DAKOTA, TEXAS, UTAH, WASHINGTON, OR WYOMING, SEND APPLICATIONS TO:

ILLINOIS, INDIANA, IOWA, MICHIGAN, MINNESOTA, MISSOURI, OHIO, OR WISCONSIN, SEN APPLICATIONS TO:

THIS IS AN APPLICATION FOR (Check appmpnafe (fern)

MATERlALS LICENSING BRANCH US. NUCLEAR REGULATORY COMMISSION, REGION 111 2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532-4352

2. NAME AND MAILING ADDRESS OF APPLICANT (Include ZIP Code)

IPE OF FEE

LICENSING ASSISTANCE TEAM DIVISION OF NUCLEAR MATERIALS SAFETY U S NUCLEAR REGULATORY COMMISSION, REGION I 475 ALLENDALE ROAD KING OF PRUSSIA, PA 19406-1415

FEE LOG FEE CATEGORY I AMOUNT RECEIVED I CHECK NUMBER I COMMENTS

NUCLEAR MATERIALS LICENSING BRANCH U S NUCLEAR REGULATORY COMMISSION REGION IV 612 E LAMAR BOULEVARD, SUITE 4 W ARLINGTON, TX 76011-4125

$

'PROVED BY DATE

0 A. NEWLICENSE

0 E. AMENDMENT TO LICENSE NUMBER

c. RENEWAL OF LICENSE NUMBER 24-24576-01

ADDRESS WHERE LICENSED MATERIAL WlLL BE USED OR POSSESSED

P.O. Box 1000 [ndependence, MO 64051-1000 or [ntersection of MO Route 7 & MO Route 78 [ndependence, MO 64051

UBMIT ITEMS 5 THROUGH 11 ON 8-112 X 11" PAPER. THE TYPE AND SCOPE OF INFORM!

Alliant Techsystems Operations Ilc Lake City Army Ammunition Plant P.O. Box 1000 Independence, MO 64051-1000

6 NAME OF PERSON TO BE CONTACTED ABOUT THIS APPLICATION

Trent Trutzel TELEPHONE NUMBER

(816) 796-7101 % 757 ( ON TO BE PROVIDED IS DESCRIBED IN THE LICENSE APPLICATION GUIDE.

RADIOACTIVE MATERIAL a Element and mass number, b chemical and/or physical form. and c maixlmum amount

which will be oossessed at anv one time 6 PURPOSE(S) FOR WHICH LICENSED MATERIAL WlLL BE USED

18. TRAINING FOR INDIVIDUALS WORKING IN OR FREQUENTING RESTRICTED AREAS INDIVIDUAL(S) RESPONSIBLE FOR RADIATION SAFETY PROGRAM AND THEIR TRAINING EXPERIENCE.

FACILITIES AND EQUIPMENT, 110. RADIATION SAFETY PROGRAM

12. LICENSE FEES (See 10 CFR 170 and Section f70.31) AMOUNT FNCLOSED

I. WASTE MANAGEMENT.

I. CERTIFICATION. (Musf be complefed by applicanf) THE APPLICANT UNDERSTANDS THAT ALL STATEMENTS AND REPRESENTATIONS MADE IN THIS APPLICATION ARE BINDING PON THE APPLICANT.

FEE CATEGORY 03710

THE APPLICANT AND ANY OFFICIAL EXECUTING THIS CERTIFICATION ON BEHALF OF THE APPLICANT, NAMED IN ITEM 2, CERTIFY THAT THIS APPLICATION IS PREPARED IN CONFORMITY WTH TITLE 10. CODE OF FEDERAL REGULATIONS, PARTS 30,32.33,34,35.38.39, AND 40, AND THAT ALL INFORMATION CONTANED HEREIN IS TRUE AND

ALSE STATEMENT OR REPRESENTATION TO

PRINTED ON RECYCLED PAPE NRC FORM 313 (3-2009)

http://infocolleas.resourc'eQnrc.gov

ATK Lake City Facility Information

Facility Background

The Lake City Army Ammunition Plant (LCAAP) was established in 1941 and was the first government-owned facility constructed to expand small arms ammunition production. Construction at the 3935-acre facility (Located at the intersection of Mo Route 7 & Mo Route 78 in Independence Missouri) began December 26,1940 and was completed October 11,1941. The government-owned, contractor-operated (GOCO) facility has operated continuously since 1941, except for a 5-year period between World War II and the Korean Conflict. From 1941 to 1985 Remington Arms was the operating contractor until Olin Corporation became the operating contractor in November 1985. Alliant Techsystems, Inc. (ATK) took over operations in 1999 and is the current operator.

LCAAP is the only provider of Department of Defense (DoD) small caliber ammunition. LCAAP orders bulk metals, chemicals, and propellants and fabricates them into complete 5.56mm, 7.62mm, and 50 caliber ammunition. LCAAP also loads, assembles, and packs 20mm ammunition. LCAAP performs reliability testing for all calibers of small arms ammunition and serves as the NATO National and Regional Test Center for ammunition and weapons testing.

Radioactive Material Use

Byproduct material is used to inspect ammunition for propellant fill height on high speed production lines. This inspection system is similar to a metal density gauge used to measure sheet metal thickness. The current systems are either one of the following:

Cesium- 137 Nuclear Research Corporation model PLG-4 (Sealed sources 3M Model 4P6E or Gamma Industries Model VDHP). There are 15 of these units not to exceed 1040 mCi or a total possession limit of 15.6 curies.

Americium-241 Alliant Techsystems (ATK) Inc. Model ATK 2010 (Sealed Sources QSA Global Model No. AMC. 19) There are 18 of these sources 1 curie each not to exceed a total possession limit of 18 curies.

Training Trent Trutzel is the current RSO he has attended a Radiation Safety Officer course presented

by Nevada Technical Associates Inc. He has a minimum of 6 years experience with radiation devices and has a B.S. Degree in Safety Management from Central Missouri State University (Now University of Central Missouri).

Michael Morton is the assistant RSO has attended a Radiation Safety Officer course presented by Engelhardt &Associates Inc. He a over 25 years of experience and a B.S. Business, B.S. Education, M.S. Technology from Central Missouri State University (Now University of Central Missouri). Mr. Morton is also a Certified Safety Professional (CSP).

Authorized Users

Dale L. Wilson, Production Electrician

Train inq Industrial Dynamics Company Factory Training Independence, MO

Nuclear Research Corp. (NRC) Factory Training Independence, MO

AB-Electron ics Central Missouri State University Warrensburg, MO

Experience: Electronics Technician Lake City Army Ammunition Plant Independence, MO

Michael Case, Shift Electrician (Electronics)

Train inq U. S. Air Force, Electronics Tech. School

Berthold Corporation Factory Training Independence, MO

Experience Shift Electrician (Electronics)

2000

1997

1982

1983 to Present

1971

1995

1982 to Present

Official Use Only - Security-Related Information

UNITED STATES NUCLEAR REGULATORY COMMISSION

REGION 111 2443 WARRENVILLE ROAO, SUITE 210

LISLE, ILLINOIS 60532-4352

RECEIVED FEB 14 2011 .-/

FEB 0 3 2011 Trent Trutzel Radiation Safety Officer Alliant Techsystems, Inc. (ATK) P.O. Box 1000 Independence, MO 64051

Dear Mr. Trutzel:

Enclosed is Amendment No. 24 to your NRC Material License No. 24-24576-01 in accordance with your request dated December 3,2010. Please note that the changes made to your license are printed in bold font.

Please review the enclosed document carefully and be sure that you understand all conditions. If there are any errors or questions, please notify the U.S. Nuclear Regulatory Commission, Region Ill office at (630) 829-9887 so that we can provide appropriate corrections and answers.

You will be periodically inspected by NRC. 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 notice of violation, or imposition of a civil penalty, or an order suspending, modifying or revoking your license as specified in the General Statement of Policy and Procedure for NRC Enforcement Actions. Since serious consequences to employees and the public can result from failure to comply with NRC requirements, prompt and vigorous enforcement action wilt be taken when dealing with licensees who do not achieve the necessary meticulous attention to detail and the high standard of compliance which NRC expects of its licensees.

Please note that by License Condition you are required to comply with the requirements of the “Order Imposing Increased Controls” (ADAMS Accession No. (ML053130218) published in the Federal Register on December I, 2005 (70 FR72128); and with the “Order Imposing Fingerprinting and Criminal History Records Check Requirements for Unescorted Access to Certain Radioactive Materials” (Fingerprinting Order) (ADAMS Accession No. (ML073230831) published in the Federal Register on December 13,2007 (72 FR 70901).

This License Condition requires that you complete implementation of said requirements by the first day that radionuclides in quantities of concern are possessed at or above the limits specified in “Table 1 : Radionuclides of Concern” contained within the fingerprinting Order, and notify, in writing, the Director, Office of Federal and State Materials and Environmental Management Programs, U.S. NRC, Washington, DC, 20555, when you have completed the requirements of this License Condition.

Our records indicate that you are not currently implementing the Increased Controls requirements.



2

Further implementation guidance and supplemental questions and answers are available for these Orders at: htt~://w.nrc.~ov/securitv/bvproduct/orders.html

NRC's Regulatory Issue Summary (RIS) 2005-31 provides criteria to identify security-related sensitive information and guidance for handling and marking of such documents. This ensures that potentially sensitive information is not made publicly available through ADAMS, the NRC's electronic document system. Pursuant to NRC's RIS 2005-31 and in accordance with 10 CFR 2.390, this letter and the enclosed license document are exempt from public disclosure because their disclosure to unauthorized individuals could present a security vulnerability. The RIS may be located on the NRC Web site at: htto://www.nrc.nov/readinq-rm/doc-collec~ions/uen-comm/re~-~ssues/2005/ri200531. Ddf and the link for frequently asked questions regarding protection of security related sensitive information may be located at: httD://www.nrc.~ov/readin~-rm/sensitive-info/faq.htmi.

Sincerely,

J Lhq- 8 R. Mulauer, .H.S. (th Physicist I

Licensing Branch

License No. 24-24576-01 Docket No. 030-28929

Enclosure: Amendment No. 24


Official Use Only - SecurityRelated Information NRC FORM 374 PAGE 1 OF 4 PAGE

U.S. NUCLEAR REGULATORY COMMISSION

MATERIALS LICENSE Amendment No. 2

Pursuant to the Atomlc Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, Code Federal Regulations, Chapter I, Parts 30, 31, 32, 33, 34, 35, 36. 39, 40, and 70, and in reliance on statements and representation heretofore made by the licensee, a license is hereby Issued authorizing the licensee to receive, acquire, possess, and transfer byproduc source, and special nuclear material designated below; to use such material for the purpose(s) and at the place($) designated below; I deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part@). This licens shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to a applicable rules, regulations, and orders of Ihe Nuclear Regulatory Commission now or hereafter In effect and to any conditions specifie below.

Licensee

I. Alliant Techsystems Inc. (ATK) Lake City Small Caliber Systems Lake City Army Ammunition Plant

Independence, MO 64051 -1 000 2. P.O. Box 1000

~~

In accordance with letter dated December 3,2010,

4. Expiration date May 31 , 201 1 5. Docket No. 030-28929

Reference No.

A. Cesium-I 37

3. License number 24-24576-01 is amended in its entirety to read as follows:

6. Byproduct, source, andlor 7. Chemical and/or physical form 8. Maximum amount that licensee may special nucfear material possess at any one time under this

license

8. Americium-24 I

A. Sealed Sources (3M Model A. 15 sources not to exceed 1040 millicuries each, total possession limit of 15.6 curies.

B. 18 sources not to exceed 1 curie each, total possession limit of 18 curies.

9. Authorized use:

A. , To be used in Nuclear Research Corporati

6. To be used in Alliant Techsystems (ATK) Inc. Moded ATK 2010 source holder for density and level measurement.

holder for level measurement.

CONDITIONS

IO. Licensed material shall be used only at the licensee's facilities located at Lake City Army Ammunition Plant, Intersection of Missouri Highways 7 and 78, Independence, Missouri.

I 1. Licensed material shall be used by, or under the supervision of, Dale Wilson, Michael Case, Michael Morton or Trent Trutzel.


Official Use Only - Security-Related Information NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION I PAGE 2 of 4 PAGES

MATERIALS LICENSE SUPPLEMENTARY SHEET

License Number 24-24576-01

030-28929

12. A.

8.

13. A.

6.

C.

D.

E.

The Radiation Safety Officer for the activities authorized by this license is Trent Trutzel.

The Assistant Radiation Safety Officer for the activities authorized by this license is Michael Morton.

Sealed sources shall be tested for leakage and/or contamination at intervals not to exceed 6 months or at such other intervals as specified by the certificate of registration referred to in 10 CFR 32.210.

In the absence of a certificate from a transferor indicating that a leak test has been made within 6 months prior to the transfer, a sealed source received from another person shall not be put into use until tested.

rces need not be leak tested if they are in storage, and are not being used. However, when they are removed from storage for use or transferred to another person, and have not been tested within the required leak test interval, they shall be tested before use or transfer. No sealed source shall be stored for a period of more than I ars without being tested for leakage and/or contamination.

The leak test shall be capable of detecting the p ce of 0.005 microcurie (I 85 becquerels) of radioactive materia e test sample. If the test reveals the presence of 0.005 microcurie (185 becquerels) or mor movable contamination, a report shall be ffled with the U.S. Nuclear Regulatory Commi immediately from s Commission regul

Tests for leakage an

I

ith 10 CFR 30.50(~)(2), and the source shall be removed in accordance with

ee or by other persons Perform such services.

14. Sealed sources containing licensed material shall not be opened or removed from their respective source holders by the licensee.

15. Installation, initial radiation survey, relocation, removal from service, maintenance, and repair of devices containing sealed sources and installation, replacement, and disposal of sealed sources shall be performed oniy by persons specifically licensed by the Commission or an Agreement State to perform such services. I

6. flotwithstanding Condition 15 , routine maintenance and servicing of devices containing licensed material shall be performed only by Dale Wilson, as described in letter dated April 23, 1998, by the manufacturer or by other persons specifically authorized by the Commission or an Agreement State to perform such services,


I .

Official Use Only - Security-Related Information NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE 3 of 4 PAGES

License Number 24-24576-01 Docket or Reference Number 030-28929


Amendment No. 24

17. The licensee shall conduct a physical inventory every six (6) months to account for all sealed sources received and possessed under the license. The records of the inventories shall be maintained for two (2) years from the date of the inventory for inspection by the Commission, and shall include the quantities and kinds of byproduct material, manufacturer’s name and model numbers, location of seated sources and the date of the inventory.

18. The licensee shall assure that the devices are tested for proper operation of the on-off mechanism and indicator, if any, at intervals not to exceed six months or at such other intervals as are specified by the manufacturer. The licensee shall maintain records of the results of these tests for a period of one year after the next required test is performed. These records shall show the date(s) of performance and results of these tests as well as the name of the individual performing the test.

19. The licensee shall operate each gauge within the manufacturer‘s specified temperature or any other

Techsystems Inc. Mo January 27,201 I,

ed Controls for Llcensees tities of Concern” (IC)

r Imposing lncreased in the Federal Register on ng Fingerprinting and

Crlmlnal History Records Check Radioactive Materials”(Fingerprintlng Order) (ADAMS Accession No. ML073230831) published in the Federal Register on December 13,2007 (72 FR 70901).

corted Access to Certain

The licensee shall complete implementation of the said requirements by the first day that radionuclides in quantities of concern are possessed at or above the limits specified in “Table I : Radionuclides of Concern” contained within the Fingerprinting Order (ADAMS Accession No. ML080160582).

Notwithstanding any provisions of the Commission’s regulations to the contrary, all measures implemented or actions taken in response to these Orders shall be maintained until the Commission orders otherwise or until the Commlsslon explicitly modifies its regulations to reflect the lncreased controls and fingerprinting requirements, and states in modifying its regulations that the revisions are to supercede these Orders.

NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION PAGE 4 of 4 PAGES License Number 24-24576-01 Docket or Reference Number 030-28929


Amendment No. 24

D. The licensee shall notify the Director, Office of Federal and State Materials and Environmental Management Programs, US. NRC, Washington, DC, 20555, In writing, within 25 days after it has completed the requirements of this condition. In addition, licensee responses applicable to this license condition shall be marked as "Security- Related Information - Withhold Under 10 CFR 2.390."

22. Except as specifically provided otherwise in this license, the licensee shall conduct its program in accordancewith the statements, representations, and procedures contained in the documents including any enclosures, listed below. The Nuclear Regulatory Commission's regulations shall govern unless the statements, representations and procedures in the licensee's application and correspondence are more restrictive than the regulations.

A. Applications dated November 29, 2000 and October 27,2006; and

B. Letters dated April 23, 1998 (with attached memorandum dated December 2, 1997), October 27, 2006, December 1 1,2006, January 22,2007, January 28,2009 (with attachments), March 23,2009, May 26,2009, December 4, 2009 (excluding the request for authorization to perform non-routine maintenance described in the third bullet), Decetnber 3, 2010 and January 27, 201 I.

FOR THE U.S. NUCLEAR REGULATORY COMMISSION

Region Ill

l i

1: Official Use Only - Security-Related Information

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Radiation Safety Procedures Revision 3 Administrative Procedure 18-42 Approved by: DCR 110531 4/27/2011 Page 1 of 9

1 .O Purpose

1 .I. This procedure outlines the duties and responsibilities of designated personnel in implementing a Radiation Protection Program for the Lake City Army Ammunition Plant.

Document No. 29 CFR 1910.96

2.0 References

Document Title

Ionizing Radiation 10 CFR

PAM 40-14

AR 385-24

Parts 19,20,30,35,40 and 290 Control and Recording ProcedureOccupational Exposure to Ionizing Exposure The Army Radiation Safety Program

Administrative 1 Procedure 18-55 Radiation Emergency Response Plan

1 NRC License NO. 24-24576-01

I DA Permit P24-01-10 I Radioactive Materials Permit

3.0 Forms Utilized

I D o c u m e n t E

1 NAVMED 6470/10

I DD 250 Form 42 I NRC/ERDA 741

I DA3337

1 NRCForm313 I ATK-5115

4.0 Reports Required

Document Title

Record of Occupational Exposure to Ionizing Exposure Radiation Request for Shipment Nuclear Materials Transaction Report Personal Exposure to Ionizing Radiation History Record Registration of Radiation Machines

~ ~~

Application for Department of the Army Radiation Authorization or Permit Application for Material License Employee Notification of Results

I Document No. 1 Document Title I ~~

I Personal Radiation Exposure Source Inventories and Leakages Disposal Permits/Authorization

I Accident Reporting

5.0 Scope

5.1. This procedure is applicable to the Lake City Army Ammunition Plant, Building 1, Building 83A, and other areas in the plant where ionizing radioactive materials may be used or stored, and areas using x-ray operations.


Adult Workers


5.2. This procedure is applicable to ensure all personnel assigned to work around radioactive materials or x-ray producing devices receive radiation doses As Low As Reasonably Achievable (ALARA). The personal exposure limits that the plant operates under are as follows:

5.0 REM/year (5,000 mREM/year) Total Effective Dose Equivalent

50.0 REM/year (50,000 mREM/year)

Em bryolFetus

1 Committed Dose Equivalent to any organ

0.5 REM/9 months (500 mREM/9 months) Total Effective Dose Equivalent (declared Pregnancy)

5.0 REM/9 months (5,000 mREM/ months)

6.0 Definitions

6.1.

6.2.

6.3.

6.4.

6.5.

ALARA (As Low As Reasonably Achievable) - ALARA means making every reasonable effort to maintain exposures to radiation as far below the dose limits as is practical, taking into account the state of technology and the economics of improvements in relationship to the benefit of the health and safety of employees and the general public.

Film Badges and Thermoluminescent Dosimeters (TLD) - An ionizing radiation-sensitive device worn by personnel, that has the appropriate sensitivity capable of determining the amount of exposure received from beta, gamma, x-ray, or neutron radiation.

High Radiation Area -An area accessible to individuals where the summation of alpha, beta, gamma, x-ray and neutron radiation levels could result in an individual receiving a dose equivalent in excess of 1 millisievert (mSv) (0.1 Roentgen Equivalent man [REM] in the international standard unit) in 1 hour at a distance of 30 centimeters from a source of radiation or from a surface that the radiation penetrates.

Ionizing Radiation - Any or a combination of the following: alpha particles, beta particles, gamma rays, x-rays, neutrons, and other nuclear particles that harm individuals because of ionizing effects.

Non-ionizing Radiation - Lasers, microwave emissions and ultraviolet (UV) light are classified as non-ionizing radiation that harms individuals due to thermal and or spectral effects.

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Radiation Safety Procedures Revision 3 Administrative Procedure 18-42 Approved by: DCR 110531 4/27/2011 Page 3 of 9 L

6.6.

6.7.

6.8.

6.9.

Millirem (mRem) - One thousandth of a Rem. A Rem is a unit of measurement of radiation- absorbed dose. When radiation penetrates living tissue, it transfers energy by ionizing tissue molecules. One Rem is the amount of radiation absorbed dose equivalent that deposits 100 ergs of energy in each gram (approximately one cubic centimeter) of tissue. One hundred Rems equal the newer international radiation absorbed dose equivalent unit of 1 Sieved (Sv).

MilliSievert (msv) - Equivalent to 0.1 Rem in the international standard units.

Digital Alarming Dosimeter - An electronic, pager-sized, digital readoutlaudio alarm dosimeter.

Radiation Area - An area where the summation of alpha, beta, gamma, x-ray, and neutron radiation levels could result in an individual receiving a dose equivalent in excess of 0.05 mSv (5.0 mRem), in one hour at a distance of 30 cm from the source of radiation or from a surface that the radiation penetrates.

6.10. Radiation Safety Officer (RSO) - The individual, who has the appropriate training and experience, designated by location management and recognized as qualified by the appropriate regulatory agency to implement the company's Radiation Safety Program.

6.1 1. Radiation Safety Committee (RSC) - The organization responsible for administering the Radiation Safety Program, in compliance with the appropriate regulatory agency requirements to minimize adverse health effects from direct or indirect exposure to ionizing or non-ionizing radiation.

6.12. Radioactive Materials - Materials possessing the property of spontaneously emitting radiant energy in the form of alpha, beta, neutron, or gamma rays by disintegration of atomic nuclei.

6.13. Restricted Area - An area where access is limited by the RSO for the purpose of protecting individuals against undue risks from exposure to sources of radiation and where an individual could receive a dose equivalent from external sources in excess of 0.02 mSv (2.0 mRem), in one hour or 5.0 mSv (500 mR) in one year.

6.14. Unattended - A radiation-producing materiaVequipment operation that is not actively monitored by an authorized radiation worker.

6.15. VisitorlTransient - A person entering a restricted or radiation area not assigned a TLD/film badge by the RSO and also as determined by organization and department instructions. The individual may be required to wear a spare or guest TLD/film badge during their time in the restricted or radiation area.

7.0 Responsibilities

7.1. The Radiation Safety Officer (RSO) is responsible for implementing the radiation safety program and ensuring those radiation safety activities are performed following approved procedures and regulatory requirements. The RSO's duties and responsibilities include ensuring:

7.1 .I. Compliance with Nuclear Regulatory Commission (NRC; 10 CFR), Department of Transportation (DOT; 49 CFR), Occupational Safety and Health Administration (OSHA; 29 CFR), and Department of the Army Regulations (AR), and material terms and conditions in the NRC license and the Department of the Army Radioactive Materials permit.

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I Radiation Safety Procedures Revision 3 Administrative Procedure 18-42 Approved by: DCR 1 10531 4/27/2011 Page 4 of 9

~

7.1.2. Individuals using gauges are properly trained. Including annual (12-month cycle) refresher training with participation in a "dry run" of emergency procedures and review of operating and emergency procedures.

7.1.3. Personnel monitoring devices are used as required and reports of personnel exposure are reviewed and disseminated in a timely manner.

7.1.4. Conduct semiannual inventories and leakage tests of the sources. Maintain calibrated radiation test equipment for testing.

7.1.5. Gauges are properly secured against unauthorized removal at all times when gauges are not in use. Notify the proper authorities in case of accident, damage to gauges, fire, or theft;

Audits are performed at least annually to ensure: 7.1.6.

7.1.6.1.

7.1.6.2.

Compliance with NRC, DOT, OSHA and Army regulations, and the terms and

The radiation protection program content and implementation criteria achieve

conditions of the license, and permits;

occupational exposures ALARA; and

7.1.6.3. Required records and information are maintained to comply with NRC requirements.

7.1.7. Results of audits, identification of deficiencies and recommended changes are documented and maintained for the required amount of time, and are provided to management for review, and prompt action taken to correct deficiencies;

7.1.8. Audit results and corrective actions are communicated to all personnel who use licensed materials.

7.1.9. Investigate all incidents, accidents and personnel exposures to radiation in excess of Part 20 limits and report them to the NRC and other authorities within the required time limits.

7.1.10. Licensed material is transported by all applicable DOT requirements.

7.1.1 1. Licensed material is disposed of properly.

7.1.12. Maintains current copies of NRC, and DOT Army regulations, reviews new or amended regulations and revises licensee procedures, as needed to comply with applicable regulations.

7.1.13. Prepare reports licenses, permits and registration applications for submission to the NRC, State of Missouri, and Department of the Army whenever there is a change in licensed activities, responsible individuals, information or commitments made during the licensing process.

7.1.14. Chairs the Radiation Safety Committee.

7.1.15. Coordinate with the emergency response and cleanup teams in of a radiation leak, as dictated by Administrative Procedure 18-55.

7.1.16. The Radiation Safety Officer (RSO) will notify the Administrating Contracting Officer and the Army Safety Officer of new sources being brought on plant and if a contractor is transporting and using sources temporally on plant so that a department of Army permit can be prepared by the Army.

7.2.1. Functions as the Radiation Safety Officer in his absence.

7.2. Alternate Radiation Safety Officer

7.3. Medical Department

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7.3.1. Performs pre-placement and termination physicals on personnel assigned to work in radiation restricted areas.

7.3.2. Ensure that workers who routinely work in the radiation restricted areas (>2.0 mR/hr or 500mR/year) are given a medical examination at least once every three years.

7.3.3. Assess injury or illness among employees who are involved in a radiation incident.

7.4. Fire Department

7.4.1.

7.4.2.

7.4.3.

7.4.4.

7.4.5.

Administer and carry out all fire protection activities consistent with Government requirements for fire and safety regulations for ammunition handling when radiation operations are in place.

Respond in event of release of radiation materials to the environment, as outlined in Administrative Procedure 18-55.

Administer necessary first aid and assist in decontamination of personnel who are involved in any accident or incident where a release of radioactive material to the environment has occurred, as outlined in Administrative Procedure 18-55.

Participates in the Radiation Safety Committee.

Fire Department needs to be informed of all radioactive sources.

7.5. Area Managers

7.5.1.

7.5.2.

7.5.3.

7.5.4.

7.5.5.

7.5.6.

7.5.7.

7.5.8.

7.5.9.

7.5. I O .

7.5.1 1.

7.5.12.

Review Standing Operating Procedures (SOP's) with employees prior to job assignment and incorporate discussion of the SOP's as a part of safety meetings.

Posts appropriate warning signs and notices.

Enforce compliance with SOP, rules and written special precautions.

Ensure that sources are secured against unauthorized use and/or theft.

Prepare, prior to the start of any operation involving radioactive material adequate SOP's for review by the Radiation Safety Officer and Radiation Protection Committee.

Report any accident or incident to the Radiation Safety Officer, where a suspected over exposure may have occurred.

In event of an emergency, follow all guidelines established in Administrative Procedure

Participates in the Radiation Safety Committee.

Ensure current copies of our NRC license, NRC Form 3 (Atomic Energy Reorganization Act), and notice of the locations of NRC regulations are posted on the department safety bulletin board.

Ensure all personnel assigned to service instruments within the restricted areas are issued and wear radiation dosimeters. Whenever the assignment requires hands-in-close work, the employees will be issued a TLD and a ring dosimeter.

Maintain record of times and dosimeters issued for personnel entering into the restricted areas.

Assure that all proper lock, tag, clear and try procedures are followed before any personnel enter the restricted areas.

18-55.

7.6. Calibration Coordinator

7.6.1. Ensure that radiation measuring instruments are calibrated on a timely basis by qualified providers.

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7.6.2. Coordinate and expedite shipping and receiving of instruments sent off plant for calibration.

7.7. General Personnel, Transient and other Operations

7.7.1. Know and follow SOP'S, rules, and written special instructions.

7.7.2. Report the occurrence of any accident or incident involving damage to the encapsulated radiation sources, to the supervisor, as soon as possible.

7.7.3. Comply with emergency procedures as outlined in Administrative Procedure 18-55 for decontamination prior to leaving the radioactive contaminated area.

7.7.4. Wear radiation dosimeters whenever handling radioactive material, or when directed by the radiation safety officer.

7.8.1. Package and ship radioactive materials in accordance with the Department of Transportation and Nuclear Regulatory Commission requirements.

7.8.2. Coordinate with the Radiation Safety Officer upon receipt of radioactive materials.

7.8. Traffic and Shipping Department

8.0 Radiation Safety Committee

8.1. Members

Radiation Safety Officer Alternate Radiation Safety Officer Fire Chief Area Manager, Building 1 Load and Assemble Area Manager, Building 83A Manager, Environmental Engineering Manager, Safety & industrial Hygiene Medical

8.2. Function

8.2.1. The Radiation Safety Committee will meet semiannually. The committee is chaired by the Radiation Safety Officer (RSO).

8.2.2. Recommend policies on the safe use, handling, storage, transport, receipt, shipment, and disposal of radioactive materials.

8.2.3. Reviews the radiation safety aspects of proposals for the procurement and use of radiation sources; the modifications of radiological operations and operating procedures. Provide recommendations to the Commander.

8.2.4. Review personal radiation dosimetry reports to ensure that radiation exposures are As Low As Reasonably Achievable (ALARA).

8.2.5. Review applications for Nuclear Regulatory Commission (NRC) licenses and Department of the Army permits.

8.2.6. Review reports of radiation incidents to determine the cause, and recommend appropriate actions to the Commander.

9.0 Training

9.1. The Area Manager is responsible for ensuring employees assigned to work in radiation areas (controlled or restricted) are adequately trained in the safety aspects of radiation exposures.

9.2. The RSO or Alternate RSO will conduct employee radiation training.

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9.3. Individuals that have not received the manufacturer's training course or equivalent initial training will be required to take an initial training course upon initial assignment to work with the radioactive materials. The course will cover:

9.3.1. Radiation Physics

9.3.1.1. Atomic and Sub-atomic Structures 9.3.1.2. 9.3.1.3. Sources of Radioactivity 9.3.1.4. Isotopes and Periodic Table 9.3.1.5.

9.3.2.1. Biological Effects of Radiation 9.3.2.2. Occupational Dose Limits 9.3.2.3. ALARA 9.3.2.4. Methods of Reducing Dose 9.3.2.5. Personal Monitoring

Radioactivity and Types of Radiation

Units of Radioactive Measurement and Half-life

9.3.2. Radiation Safety

9.3.3. Regulatory Requirements

9.3.3.1. Licensing 9.3.3.2. Storage of Licensed Material 9.3.3.3. 9.3.3.4. Leak testing 9.3.3.5. Inventory 9.3.3.6. Maintenance 9.3.3.7. Operating and Emergency Procedures 9.3.3.8. Audits 9.3.3.9. Record Keeping 9.3.3.10. Disposal 9.3.3.1 I. Incidents

Constant Control and Surveillance of Radioactive Materials not in Storage

9.3.4. Gauge Theory, Operation and Field Training

9.3.5. Emergency Procedures Personal Monitoring

9.3.6. Written Test and Test Review

9.4. Employees that work on the radiation devices must be trained in accordance with NRC regulations and any stipulations stated in the specific NRC license. These persons will be listed on the license as authorized users.

9.5. Annual follow up training will be conducted annually (1 2-month cycle) after the initial training. The course will include a "dry run" of emergency procedures and a review of:

9.5.1. Operating and emergency procedures. 9.5.2. DOT requirements. 9.5.3. Changes in applicable regulations or license conditions. 9.5.4. Deficiencies identified during the performance of annual audits of radiation safety

program. 9.5.5. Any applicable NRC Informational Notices, Bulletins, or Newsletter articles.

9.6. The Safety Department will document training, maintain official training records, and input training information into electronic database.

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I 10.0 General

10.1. Changes to any statements contained in the application must have prior approval of the

10.2. For interpretation of uncertain aspects of this procedure, SOP'S or of the reference documents,

10.3. Changes necessitated by new developments, or by the requirements of higher headquarters

10.4. Violations of these procedures will be reported through responsible person to the Radiation

Nuclear Regulatory Commission (NRC).

the RSO will be consulted.

will be effected by written notice and revision to this procedure.

11.1. No controlled radioactive material will be received at the plant until it has been checked and

11.2. In general, the radioactive material will be delivered to the designated area by the common I

approved by the Radiation Safety Officer.

carrier. The Receiving Department will notify the Radiation Safety Officer, so that the shipment can be checked for contamination prior to unloading.

11.3. No shipments will be received without a one-day notice.

12.1. Every effort will be made to keep the exposure As Low As Reasonably Achievable (ALARA).

12.2. Personal dosimetry will be used as required by the provisions of 10 CFR 20, AR 40-14, and

12.3. Radiation dosimetry is required if there is any chance that an individual will be exposed to one-

12.4. Dosimeters will be analyzed by a NVLAP accredited, NRC licensed or agreement state facility.

12.4.1. Approved Standing Operating Procedures will be posted. All unauthorized personnel will

12.4.2. Radiation monitoring equipment will be calibrated on an annual basis, or as otherwise

12.0 External Exposure to Radiation

Time, distance, and shielding will be used.

AR 385-24.

tenth the annual limit.

be excluded from the radiation areas.

specified by the U. S. Army. Each instrument will be calibrated to NlST traceable sources by a NRC licensed calibration facility.

12.4.3. The Radiation Safety Officer or designate will periodically (quarterly) monitor the NRC radioactive licensed sources, to ensure controlled and restricted area boundaries are appropriately established.

13.0 Internal Exposure to Radiation

13.1. Radiation sources, listed on NRC licence 24-24576-01 and/or DA Permit P24-01-10, will be

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14.0 Audits

14.1. The Radiation Safety Officer will ensure that the area around NRC Specific licensed sources are monitored at least quarterly, to ensure boundaries (between controlled and restricted areas) are appropriately established. Records will be kept on file until a NRC auditor has reviewed them.

semiannually (minimum 6-month intervals) to determine if there is any significant leakage (0.005 microcuries or 185 Bq) from the NRC Specific and General (as required) licensed sources. Records will be kept on file until a NRC auditor has reviewed them.

14.3. The Radiation Safety Officer will ensure that an annual internal audit is performed to determine compliance with our local radiation protection program and NRC regulations. Records will be retained for at least three years.

14.2. The Radiation Safety Officer will ensure that swipe samples are taken and analyzed at least

Changes Revision 2 (DCR 080945) Revision 3 (DCR 1 1053 1)

AP 1 8-42


Title 29 CFR 1910.96

Radiation Emergency Response Plan Administrative Procedure 18-55 Amroved bv: DCR 110531 41271201 1

Ionizing Radiation

Revision 1 Page 1 of 5

NRC/ERDA 741 DD 250 Form 42

1.

2.

3.

4.

Nuclear Materials Transaction Report Request for Shipment

Purpose

1.1. This procedure prescribes the Lake City Army Ammunition Plant emergency response policies and procedures relative to the release or potential release of radioactive material in the SCAMP Load and Assemble Wing in Building 1 and the TNR Reaction Wing in Building 83A.

References

I Document No. I Document Title 1

1 Title 10 CFR 1 Parts 19 and 20 I I PAM 385-24 I Army Radiation Safety Program

~ _ _ _ ~~ ~~

Nuclear Regulatory Commission (NRC) License 24-24576

Forms Utilized

1 Document No. 1 Document Title I

Reports Required

I Document No. 1 Document Title

Source Inventories and Leakages Disposal Permits/Authorization

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5. Scope

5.1. This procedure outlines a set of guidelines, written in accordance with Army Regulation (AR) 385-24, to assist operations and technical staff in event of an accident involving; the fifteen sources (A combination of Americium-241 [Am-2411 or Cesium137 [Cs-I 37) located in the Loading Wing in Building 1; one Cs-137 source located in the TNR Reaction Room in Building 83A.

5.2. The five loading machines in Building 1 are each equipped with three Am-241 gauges or three Cs-137 gauges. They are a part of the system used to measure propellant powder depth inside loaded ammunition cases. Each Am-241 device housing has been tested in accordiacne with IS0 291 9: 1999(E) and is made of tungsten and stainless steel.

detection system for the reactor vessel. This source is sealed in an explosion proof lead lined container to protect it from fire hazards present in the operation.

5.4. All machines and radioactive sources located in Building 1 are protected by high-speed deluge systems.

5.5. In case of a fire or explosion the Fire Department will evacuate and secure the area, and will assess the extent of any damage to the radioactive sources. If the fire or exdosion involved any of the radioactive sources, the Radiation Protection Officer (RPO) will determine if leakage occurred.

5.3. The Cs-I 37 source in the TNR Reaction Wing, Building 83A is used as part of the foam

6. Responsibilties

6.1.1. Ensure employees working near radioactive sources are aware of the location of the source and the possibility that a radiation incident could occur.

6.1.2. Ensure personnel know and follow established shutdown and evacuation procedures for fires and explosions. Unless conditions dictate otherwise, personnel will assemble at the designated locations. No one will reenter the building until the RPO deems the environment throughout the building to be free from radiation.

6.1. Production Foreman, Loading and Assembly will ensure:

6.2. Radiation Protection Officer (RPO), or alternate RPO will ensure:

6.2.1. Conduct an annual drill to practice the procedures outlined in this document.

6.2.2. After a fire or explosion involing the radioactive sources, monitor controlled and restricted areas to determine if contamination is present. If contamination is found, establish boundaries to prevent contamination from spreading.

of contamination and to assess individual exposure.

Coordinate with medical personnel to determine if contaminated victims should be transported to an emergency care facility prior to being decontaminated.

will not be considered radioactively clean until it is thoroughly inspected.

and Security during and following an emergency to contain, and remove the radioactive contamination.

6.2.3. Ensure personnel involved in the incident or cleanup are monitored to prevent the spread

6.2.4. Determine effectiveness of decontamination efforts using field survey equipment.

6.2.5. Oversee the clean up, containerizing and disposal of radioactive Contamination. The area

6.2.6. Coordinate with the Hazardous Material Emergency Response Team, Fire Department,

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6.2.7. If necessary, notify by telephone the Nuclear Regulatory Commission (NRC); the manufacturer's of the radioactive sources; and government safety office of the fire or explosion.

CommanderlACO and the Nuclear Regulatory Commission (NRC). 6.2.8. Prepare and provide a complete history of the incident and contamination operation to the

6.3. Security will secure the area to prevent unauthorized personnel from entering contaminated areas.

6.4. The Fire Department, once the emergency is under control, will remain on the scene to assist the Radiation Protection Officer (RPO) and the Emergency Response Team to do the following:

6.4.1. Ensure all personnel use appropriate personal protective equipment and respiratory

6.4.2. Keep water from coming in contact with the radioactive sources;

6.4.3. Control runoff, prevent it from entering the sewer system, or overflowing outside through

6.4.4. Ensure the air handling system is shutdown, and all vents are closed. The air handing

protective equipment before reentering the area;

the doorways until it has been monitored; and

system will be shutdown when the deluge system is operational.

6.5. Hazardous Material Emergency Response Team

6.5.1. Receive training on health hazards and safety precautions of radiation, and radiation survey meters. The team will hold an annual drill on how to use radiation survey meters, and decontamination methods of personnel and areas.

6.5.2. Work with the Radiation Protection Officer (RPO) to decontaminate personnel, facilities, and equipment in event of a radiation incident;

6.5.3. Control runoff, prevent it from entering the sewer system, or overflowing outside through doorways until it has been monitored;

6.5.4. Maintain emergency response equipment to respond to a radiation emergency.

7. Procedures

7.1. Fires and Explosions involving isotopic gauges

7.1.1. In event of a fire or explosion the established evacuation plan will be implemented, that includes the activation of the automatic deluge water system and the shutdown of the ventilation system.

7.1.2. Persons involved in the evacuation will remain at the designated meeting location until an all clear is given. The Fire Chief and the Radiation Protection Officer (RPO) will evaluate the extent of the contamination released before providing the all clear signal.

apparatus (SCBA) when responding to an incident.

extent of involvement of the sources will be made by the Fire Chief (or Fire Captain, in the absence of the Fire Chief).

7.2. The Radiation Protection Officer (RPO) will be notified, and if any sources appear to have been

7.1.3. The Fire Department will wear full protective clothing and self-contained breathing

7.1.4. After the fire emergency is terminated, the water will be shut off and a determination of the

involved in the incident, the following will be executed.

7.2.1. Control runoff, prevent deluge water from entering the sewer, or overflowing outside through doorways until it has been monitored.

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7.2.2. Emergency medical personnel will determine if any employee involved in the incident was

If so, patients will be considered to be contaminated with radioactive material, until

injured and if the injuries require immediate medical attention.

7.2.2.1. there is an indication to the contrary. They will be transported to the nearest medical treatment facility. A blanket or sheet will be used to reduce the spread of contamination in the ambulance. Emergency medical personnel will inform the treatment facility of the patients' potential contamination prior to their arrival.

site until the presence of radioactive contamination has been determined, and decontamination is completed.

7.2.2.2. If not, patients will be stabilized by emergency medial personnel and remain on

7.2.3. The Radiation Protection Officer (RPO) will wear full protective clothing and Self-contained breathing apparatus (SCBA) level B protection when responding to an incident where radiation leakage may have been identified. The RPO will make a determination if any source has leaked radioactive material. If so, notification will be made to the NRC, U.S. Army, and the manufacturer of the source (QSA Global).

7.2.4. Boundaries will be established to prevent any spread of contamination. If radioactive contamination is found, a decontamination, and staging area will be set up. Anyone entering or existing the contaminated area will pass through the decontamination area.

7.2.5. If radioactive contamination is found, the Radiation Protection Officer (RPO) will ensure personnel involved in the incident or cleanup are monitored and decontaminated as required. Priority will be given to injured personnel. Monitoring is performed to prevent the spread of contamination and to assess individual exposure.

7.2.5.1. Decontamination will be performed by the Hazardous Materials Emergency Response Team

7.2.5.1 .I.

7.2.5.1.2.

7.2.5.1.3.

7.2.5.1.4.

7.2.6. If source leakage has occured, deluge water and any solid (brown granules, like sand) contamination will be vacuumed into 55-gallon drums using a H.E.P.A. filtered, explosion proof, wet/dry vacuum. Waste materials will be containerized, labeled and held for disposal as prescribed by the NRC and U.S. Army.

Contaminated clothing will be removed.

Contaminated skin will be cleaned with waterless soap and paper towels.

Waste materials will be containerized, labeled and held for disposal as

Personnel are monitored after decontamination to ensure effectiveness of

prescribed by the NRC and U.S. Army.

decontamination.

7.2.6.1. Potential contamination will be identified by using survey meters. Samples of

7.2.7. Personnel entering the contaminated area will wear Thermal Luminescence Devices (TLDs) or direct reading monitors (to measure their exposure), personal protective clothing and self-contained breathing apparatus (SCBA) level B protection. Personal protective clothing and equipment will be decontaminated or doffed, containerized, labeled and held for disposal as prescribed by the U.S. Army prior to leaving the area.

7.2.8. Personnel entering the contaminated area will, at the minimum have attended a 24-hour, Hazard Waste Operations (HAZWOPER) training course, and have had eight hours of supervised on-the-job training, per 29 CFR 1910.120.

7.2.9. The Radiation Protection Officer (RPO) will ensure the area has been thoroughly decontaminated prior to release to unprotected personnel.

contaminated water will be collected for further analysis.

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Revision 1 Approved by: DCR 1 10531 4/27/2011 Page 5 of 5

7.2.1 0. Medical personnel and the Radiation Protection Officer (RPO) will assess potentially exposed personnel and document their exposure.

8. List of Required Equipment

8.1. Geiger counters

8.2. TLDs or Direct Reading Dosimeters

8.3. Mini-scaler or Scintillation Meter

8.4. Level B protective equipment

8.4.1. Self-contained Breathing Apparatus (SCBA)

8.4.2. Full body suits, rubberized

8.5. H.E.P.A. filtered, explosion proof, wetldry vacuums 8.6. Decontamination materials

8.6.1. Emergency response trailer

8.6.1 .l. Water hoses

8.6.1.2. Brushes

8.6.1.3. Plastic drop cloths

8.6.1.4. Wading pools

8.6.1.5. Tyvek coveralls

8.6.2. Waterless soap, and paper towels

Changes Revision 1: (DCR 11 0531)

AP18-55

Radiation Safety Officer

s2yh&& 1 3 - 17f 2004

(RADIATION SAFETY OFFICER RADlAl The Instructors: In order to conserve space in this brochure, we have not included information about the course instructors. Information about the instructors can be obtained on the web (http://www.ntanet.nethstructors.httd ) or you can call us an we will send you the information by fax. RSgis$. Pf! tion Information: To register for a course, you may fill out the attached registration form and fax or mail it to us. Phone registrations are also accepted. Payment for a course can be han- dled by purchase order or credit card. We will send a fax confirnation when you register for a course. The confirmation will have information about the course location and also information about reduced hotel room rates fox attendees. Please wait until you receive the confiiation before making your hotel arrangements. In order to be properly registered for a course, you must receive a confiiation, so please call us if you have not received i t We encourage everyone to request a course outline before registering for a course, to insure that the content is suitable for your needs. 1. Radiation Safety officer ($1100) Las Vegas, January 12 - 16.2004, March 15 - 19,2004. May

2004, November 8 - 12,2004. This course will also be given in Rochester, New York, September 13 - 17,2004 and in Columbus, Ohio, March 8 - 12 2004. This course is &signed to provide the technical and practical information needed to prepare a person to be an effective radiation safety officer. It will also be useful as general introductory training for anyone who works with radioactive materials or who may be required to be an alternate radiation safety officer. (Those who have no prior experience in radiation safety are encouraged to take our CD-ROM course before attending this course.) Topics to be covered include atomic structure, properties of ionizing radiation, shielding, radiation and biological safety terms and Units, biological effects of radiation exposure, radiation detection and measurement, state and federal regulations, dosimetry, emergency procedures, recordddocu- mentation and transportation regulations. The course instructors in Las Vegas will be Ted Allen and Robert Holloway. The courses in Rochester and Columbus will be taught by Andrew h a m . The above courses will be held at hotels and attendees will receive special rates by mentioning that they are attending the class. Complete details about the meeting place will be included in the confirmation of your registration. The reduced rates are not available if reservations are made less than 30 days

17 - 21, 2004, July 12 - 16, 2004, %pt 13 - 17,

. . . . . . . . . . . "̂ .. . . . . . . . . . . . . . . . . . . . . . . . . ......... .-__-...I____ -̂- ........................ ._ ........ .--

http://www.ntanet.nethstructors.httd

Radiation Inventory Master List

Activity 2.0 Ci

Half life 30.17 years 2.0 Ci



Half life 30.17

1

Physical Form

L-Liquid S- Solid G--

S

S

S

S

End Item Description Model PLG-4

SN1400C guage source, Line 1

Swip Test Required?

YeslNo

Yes 74000 M bq

Yes 74000 Mbq

Yes 74000 Mbq

Model PLG-4 SN1401C guage source, Line 1

Date of Physical InventoQ

Model PLG-4 SNI 399C guage source, Line 1


Half life 30.17 years

2.0 Ci Half life 30.17 years 2.0 Ci

Half life 30.17 years

Model PLG-4 SN1410CL

guage source,

S

S

S

Manufacture1 NUCLEAR

RESEARCH CORP (NRC)

NUCLEAR RESEARCH CORP (NRC)

NUCLEAR RESEARCH

CORP (NRC)


Isotope Cesium

137 cs- I 37

peta/Gam. Cesium

137 cs- I 37

peta/Gam. Cesium

137

peta/Gam. Cesium

1 37 cs-I37

CS-I 37

Line 2 I I peta/Gam. ModelPLG-4 I NUCLEAR I Cesium


Model PLG-4 SN141 I C guage source, Line 3


SN1408C guage RESEARCH 137 source, Line 2 CORP (NRC) Cs-137

peta/Gam. Cesium

137 cs- I 37

peta/Gam.

Cesium 137

cs- I 37 peta/Gam.

Cesium 137

cs- I 37 peta/Gam.

I I NUCLEAR

RESEARCH CORP (NRC)



S-Sealed or U-

Jnsealed source

S

S

S

Security Controls idequate?

YIN Y

Y

Y

74000 Mbq -+ Yes

74000 Mbq

Yes 74000 Mbq

Yes 74000 Mbq

Yes 74000 Mbq


Isotope Cesium

137 CS-137

peta/Gam. Cesium

137 CS-137

peta/Gam. Cesium

137 CS-137

2

Physical Form

L-Liq uid S- Solid

Activity G G ~ ~ 2.0 Ci S

Half life 30.17 years 2.0 Ci S

Half life 30.17 years 2.0 Ci S

Half life 30.17

Reporting

Radioactive Material End Item

Swip Test Required?

YeslNo

Date of Physical lnventow

137 Half life CS-I37 I 30.17 I

MSC ,CMP

,CMP

.CMP

,CMP

.CMP

. C a p

.CMP

. C a p

.CMP

peta/Gam. I years I Cesium I 2.0 Ci I S

-

Activity Location Description Manufacturer ATTNlSOSLC-SF Bldg. 1 Model PLG-4 NUCLEAR

Independence, Loading Wing, SN1413CL RESEARCH module 3 guage source, CORP (NRC)

Line 3

MO

ATTNzSOSLC-SF Bldg. 1 Model PLG-4 NUCLEAR Independence, Loading Wing, SN1402C guage RESEARCH

module 4 source, Line 4 CORP (NRC)

ATTN:SOSLC-SF Bldg. 1 Model PLG-4 NUCLEAR Independence, Loading Wing, SN1403C guage RESEARCH


MO

MO

ATTN:SOSLC-SF Bldg. 1 Model PLG-4 NUCLEAR Independence* Loading Wing, SN1404C guage RESEARCH


ATTNLSOSLC-SF Bldg. 1 Model PLG-4 NUCLEAR Independences Loading Wing, SN 141 4C guage RESEARCH






ATTNlSOSLC-SF Bldg. 1 Model 492 J.L. Sheapard

MO

MO

MO

MO

custom (ATK cutom

ATTNlSOSLC-SF Bldg. 1 Model 492 J.L. Sheapard Independence, Loading Wing custom (ATK cutom

Independence, Loading Wing old G&W SN15014 device)

MO

old G&W SN15016 device) MO

peta/Gam. Cesium

137 Half life CS-137 I 30.17 I

years 2.0 Ci S

petalGam. I years I Americium I 1.0 Ci I S

peta/Gam. Cesium

AM-241

AM-241

years 2.0 Ci S

S-Sealed or U-

Unsealed source

S

S

S

Security Controls idequate;

YIN

Y

Y

Y

Yes 1 74000 Mbq

74000 Mbq

74000 M bq

74000 Mbq +- 74000 M bq

74000 Mbq

Yes I

MSC L C M p

L C M p

L C M p

I I Mo

Reporting Activity

Independence, MO

ATTNSOSLC-SF

ATTN:SOSLC-SF Independence,

MO

ATTNlSOSLC-SF Independence,

Physical F~~~

L-Liquid S- Solid

S

Independence,

S-Sealed Security or U- Controls

Unsealed Adequate?

S Y source YIN

Independence.

Independence,

SN15017 Model 492

Radioactive Material Location Bldg. 1

Loading Wing old G&W Bldg. 1

device) gamma J.L. Sheapard Americium 1 .O Ci

Loading Wing old G&W

S

S

S

S

S

S

S

S

S

S

Bldg. 1 Loading Wing

S Y

S Y

S Y

S Y

S Y

S Y

S Y

S Y

S Y

S Y

old G&W - Bldg. 1

custom SIN-TBD

Model 492 custom SIN-TBD Loading Wing

old G&W

(ATK cutom AM-241 device) gamma

(ATK cutom AM-241 J.L. Sheapard Americium 1 .O Ci


old G&W Bldg. 1

L C M p

L C M p

L C M P

L C M p

L C M p





MO


MO

ATTNlSOSLC-SF Independence,

MO


MO


MO


old G&W Bldg. 1

custom SIN-TBD

Model 492 custom S/N-TBD




(ATK cutom AM-241 J.L. Sheapard Americium 1 .O Ci


custom SIN-TBD

End Item

custom


custom SIN-TBD( (ATK cutom I AM-241 I I device) I g amma I J.L. Sheapard I Americium I 1 .O Ci Model 492

I device) I g amma I J.L. Sheapard I Americium I 1 .O Ci Model 492

I device) I g amma I J.L. Sheapard I Americium I 1 .O Ci Model 492

I I device) I g amma Model 492 I J.L. Sheapard I Americium I 1 .O Ci

pustom SIN-TBD (ATK cutom AM-241

l 1 device) 1 gamma 1

pustom SIN-TBD (ATK cutom AM-241 Model 492 J.L. Sheapard Americium 1 .O Ci

I device) I g amma I J.L. SheaDard I Americium I 1 .O Ci Model 492

3

I

Yes I

Yes

Yes

Yes

Yes I

* Yes


Physical Form SSealed Security

Radioactive L-Liquid or U- Controls Swip Test Date of Reporting Material End Item S- Solid Unsealed Adequate? Required? Physical

YeslNo Inventory YIN source

S S Y

S S Y

Activity Location Description Manufacturer Isotope Activity G-Gas ATTNISOSLC-SF Bldg. 1 Model 492 J.L. Sheapard Americium 1 .O Ci

Independence, Loading Wing custom SIN-TBD (ATK cutom AM-241

old G&W device) gamma ATTN:SOSLC-SF Bldg. 1 Model 492 J.L. Sheapard Americium 1 .O Ci

Independence, Loading Wing custom SIN-TBD (ATK cutom AM-241 old G&W device) qamma

ATTN:SOSLC-SF Bldg. 1 M u Model 703 Tritium 200 mCi G Independence, ATK Safety SN7030839

Yes MO

Yes MO

S Y H-3 MO

No Department static tester Peta off ice LCAAP 90036 Tritium H-3

S Y ATTN:SOSLC-SF Bldg. 1 M u Model 703 Tritium 200 mCi G H-3 Independence, ATK Safety SN1699 static

MO No Department tester LCAAP Peta

office 9881 5 Tritium H-3 S Y ATTN:SOSLC-SF Bldg. 1 M u Model 703 Tritium 200 mCi G

H-3 Independence# ATK Safety SN3262 static MO

No Department tester LCAAP Beta off ice 88742 Tritium H-3

S Y ATTN:SOSLC-SF Bldg. 1 M u Model CS-7D Cesium 1.02 pCi S 137

off ice check source Peta

Independence, ATK Safety SN 1508193, MO

Department Calibration CS-I 37 No 0.038 Mbq

S S Y ATTN:SOSLC-SF Bldg. 1 M u Model CS-7C Cesium 0.097 137 pCi

Beta No

137 VCi

Independence, ATK Safety SN 1507193,

office check source

MO Department Calibration cs-I 37

0.004 Mbq S S Y ATTN:SOSLC-SF Bldg. 1 M u Model 696431, Cesium 0.005

Independence* ATK Safety calibration MO

No 0.0002 Mbq

Department check source cs-I 37 off ice Beta

4


MSC LCAAP

5

Radioactive Reporting Material Activity Location

ATTN:SOSLC-SF Bldg. 6 Independence, Chemistry Lat

MO

Isotope Activity Nickel 63 15 mCi

Ni-63 Peta

I ofice I

Physical Form

L-Liquid S- Solid G-C;

S

Swip Test Required?

YeslNo

LCAAP 91689 Model 7000UF

Date of P h y s ica Inventor

point meter SN10344p Dew I

End Item Description Model 0330-

01 19 SN3044, Perkins Elmer

Gas

WM2464 Model 7000UF

Manufacture

Doint SN22421p meter Dew WM I No

0.259 Mbq

No 0.259 Mbq

No In Storage 18500 Mbq

Yes 1.295 Mbq

Yes 370 Mbq

2459 I ModelPLG-3 I NUCLEAR

G e n a 3 licensed device

Genaral licensed device

CORP (NRC)

SN29536, Dew point meter

ATK 001 182 Model ltemizer 3 ;NO5044901 025

2 LCAAP 103373

Geion Track

Cesium 137

cs-I37 Peta

Radium 226 Ra

226

Half life 30.07

alpha Radium 7pCi S

226 226 Rai I alpha

Radium 7pCi S

Ra-226 226 I I alpha I I

Americium I 500 mCi I S 241 m

gamma Americium

241 m

AM-241

AM-241

+ 35 pCi

alpha Nickel 63 10 mCi

Ni-63 Peta

S-Sealed or U-

Jnsealed source

S -

S

S

S

S

Security Controls

Adequate YIN Y -

Y

Y

Y

Y

I

3700 Mbq Genaral licensed device

0.259 Mba

MSC LCAAP

ndependence, Security Mo I Storage Roon

Radioactive Reporting Material Activity Location

Independence, Security ATTN:SJMLC-SF Bldg. 7

Storage Roon MO

I I

Physical F~~~

L-Liquid S- Solid

I I

SSealed Or "-

Unsealed Isotope

Nickel 63 Ni-63 Beta

Nickel 63 Ni63 Beta



End Item Description Activity

10 mCi

10 mCi

10 mCi

10 mCi

Model Vaportracer 2

3N0903493845( LCAAP I03322

Geion Track

Model Vaportracer 2

SN0903493847! LCAAP I03323

Geion Track

4PD 2000 Mode

SIN 4234 LCAAPlO3755

# 2428800-30

LCAAP ATWSJMLC-SF Independence,

MO

4PD 2000 Mode

SIN 4231 LCAAPI 03756

# 2428800-30

off ice

Bldg. 1 M u ATK Safety Department

off ice


~~

Hanufacturer

Smith Detection

Smith Detection

Security Controls 4deq uate?

YIN Y -

Y

Y

Y

Swip Test Required?

YeslNo

Yes 370 Mbq

Yes 370 Mbq

Yes 370 Mbq

Yes 370 Mbq

6

Date of Physical Inventory

The yellow highlighted areas are sources that must be added to the Materail License.

X-Ray source is registered with the Missouri Department of Health. Gam. Gam.- Gamma

Point of Contact - Trent Trutzel & Mike Morton 816-796-7443, Cindy Park 816-796-7195

The following regualtion was used for requiring a swipe test: 10 CFR 39.35 Leak Testing of Sealed Sources (2)(e) Exemptions from testing requiremts. The following sealed sources are exempt from the periodic leak test requirements set out in paragraphs (a)

though (d) of this section: (1) Hydrogen3 (tritium) sources; (2) Sources containing licensed material with a half-life of 30 days or less; (3) Sealed sources containing licensed material in gaseous form;


Physical F~~ S-Sealed Security

Radioactive L-Liquid or U- Controls Swip Test Date of Reporting Material End Item s- Solid Unsealed Adequate? Required? Physical

MSC Activity Location Description Manufacturer Isotope Activity G- source YIN YeslNo Inventory A

7

The following Items have be deleted form the Inventory andlor removed from the plant, that may have been on previous inventories.

I I

Model FT- 5OB/PL SN

114281, Measurement

guage, 7.62mm Model FT- 5OC/PL SN

1 16253, Measurement

guage, 7.62mm Model FT- 5OC/PL SN

1 16254, Measurement

guage, 7.62mm

X-Ray Inventory

SSealed or U-

Unsealed source

N/A

N/A

N/A

N/A

I ~~

Security Controls

Adequate? YIN Y

Y

Y

Y

MSC LCAAP

Swip Test Required?

YesINo N/A

N/A

N/A

N/A

N/A

N/A

N/A

LCAAP

Date of Physical Inventory

LCAAP

Activity Dose at

LCAAP

G - G ~ ~ N/A

Reporting Activity

Independence, MO

ATTN:SJMLC-SF

38 cm 45mR

Dose at 38 cm 45mR

Dose at 38 cm 45mR

Dose at 38 cm 45mR

ATTNlSJMLC-SF Independence,

MO

N/A

N/A

N/A

ATTN: SJMLC-SF Independence,

MO

LCAAP

LCAAP

ATTN:SJMLC-SF Independence,

MO

ATTNlSJMLC-SF Bldg. 6 independence, Chemistry

Lab Metallurgy

MO

ATTN:SJMLC-SF Bldg. 8 Bay E Independence,

Radioactive Material Location

LCAAP

Trailer in Front of Bldg. 3 Souteast parking lot

Trailer in Front of Bldg.

3 Souteast parking lot

Trailer in Front of Bldg, 3 Souteast parking lot

Trailer in Front of Bldg. 3 Souteast parking lot

ATTN:SJMLC-SF Bldg. 8 Bay E Independence,

MO

End Item Description

Pulserad Flash X- ?ay SystemsMode 43733A S/N K99-

3PB-001

Pulserad Flash X- Zay SystemsMode 43733A S/N K99-

3PB-002

Pulserad Flash X- ?ay SystemsMode 43733A S/N K99-

3PB-003

Pulserad Flash X- ?ay SystemsMode 43733A SIN K99-

3PB-004

Electron Microscope Model

DSM 960A LCAAP # 97923

Pulserad Flash X- iay SystemsMode 43734A S/N A06-

4PC-042

Pulserad Flash X- iay SystemsMode 43734A SIN A06-

4PC-043

Vlanufacturei Titan System: Corporation

Titan System: Corporation

Titan System! Corporation

Titan System: Corporation

Zeiss Germany

-3 a Divison o Titan

Corporation

-3 a Divison o Titan

Corporation

Isotope X-Ray

Voltage 300kV

X-Ray

Voltage 300kV

X-Ray

Voltage 300kV

X-Ray

Voltage 300kV

X-Ray

Voltage 30 kv

X-Ray

Voltage 450kV

X-Ray

Voltage 450kV

output

output

output

output

output

output

Output

Physical Form

L-Liquid S- Solid

meter

meter -T- I

X-Ray inventory

Bldg. 8 Bay 9

Bldg. 8 Bay 9

Bldg. 8 Bay 9

Bldg. 8 Bay 9

Bldg. 8 Bay 9

Bldg. 8 Bay 9

Bldg. 8 Bay 9

.CAAP

.CAAP

.CAAP

.CAAP

.CAAP

- X A A P

X A A F

Pulserad Flash X- Ray SystemsMode 43731A S/N A06-

4PC-051


4PC-062


4PC-063


4PC-064

Pulserad Flash X- Ray SystemsMode 43731A SIN A06-

4PC-065


4PC-066


4PC-067


MO


MO


MO


MO

ATTN :SJMLC-SF Independence.

MO

ATTN:SJMLC-SF Independence,

MO


MO

X-Ray Output Voltage 150kV


X-Ray Output

Dose at N/A 20 cm 40mR


Dose at N/A 20 cm

L3 a Divison of Titan

Corporation


Corporation


Corporation


Corporation


Corporation


Corporation


Corporation

Voltage 150kV





40mR



Dose at NIA 20 cm 40mR


X-Ray Inventory

LCAAP

LCAAP

LCAAP

LCMP

ATTNSJMLC-SF Bldg. 8 Bay 9 Pulserad Flash X- L3 a Divison of X-Ray

43731A SIN A06- Corporation Voltage 4PC-068 150kV

ATINSJMLC-SF Bldg. 8 Bay 9 Pulserad Flash X- L3 a Divison of X-Ray

43731A SIN A06- Corporation Voltage 4PC-069 1 50 kV

ATTN:SJMLC-SF Bldg. 8 Bay 9 Pulserad Flash X- L3 a Divison of X-Ray

43731A SIN A06- Corporation Voltage 4PC-070 150kV

ATTN:SJMLC-SF Bldg. 3 Rapiscan Model Rapiscan an X-Ray independence, #522B SIN OS1 Systems Output

70405N07 Company Voltage 140kV

Independence, Ray SystemsModel Titan output MO

Independence, Ray SystemsModel Titan output MO

independence, Ray SystemsModel Titan output MO

MO

The following Items have be deleted form the Inventory andlor removed from the plant, that may have been on previous inventories.

LCAAP ATTN:SJMLC-SF Bldg. 8 Bay 9 Pulserad Flash X- L3 a Divison of X-Ray Dose at N/A NIA Y NIA Independence, Ray SystemsModel Titan Output 20 cm

43731A SIN A06- Corporation Voltage 40mR MO

4PC-051 150kV

L C M P ATTN:SJMLC-SF Bldg. 8 Bay 9 Pulserad Flash X- L3 a Divison of X-Ray Dose at NIA N/A Y NIA , , independencei Output 20 cm ,Ray SystemsModel Titan 43731A S/NA06- I Corporation I Voltage 1 40mR I I I I I 1 I MO

4PC-052 150kV

NIA I Y I NIA I I LCAAP ATTN:SJMLC-SF I Bldg. 8 Bay 9 I Pulserad Flash X- I L3 a Divison of I X-Ray I Dose at I N/A I Indc

437: MU

4PC-051 150kV

L C M P ATTN:SJMLC-SF Bldg. 8 Bay 9 Pulserad Flash X- L3 a Divison of X-Ray Dose at NIA NIA Y NIA indc

I 4PC-052 I I I

Exit Sign Inventory (Containing Radiation)

Radioactive lllaterial Location Building 3 Annex

50cal PrimeILoad Lower level south

double door

Building 3 Annex

50cal PrimeILoad M e u level East

double door

Building 3 Annex

.50caI PrimeILoad M e u level West

double door

Building 3 Annex

.50cal PrimeILoad Lower level North

west door

MSC LCAAP

LCAAP

LCAAP

LCAAP

LCAAP

End Item Description Manufacture1

Exit Sign lsolite SIN: 241370 Model:

SLZ-6O-S-S- 20-BK-U


SLZ-6O-S-S- 20-BK-U


SLZ-6O-S-S- 20-BK-U

Exit Sign lsolite SIN: Y66241 Model:

2040

~ ~~

Reporting Activity

Independence, MO

ATTN:SJMLC-SF


MO

ATTN:SJMLC-Sf Independence,

MO

ATTN:SJMLC-Sf Independence ,

MO

ATTN:SJMLC-SI Independence,

MO

Swip lest qequired?

Date of Physical

Building 3 Annex

SOcal PrimeILoad Lower level North

double door

Exit Sign SIN: Y66238

lsolite Model: 2040

I I

Isotope Tritium 20 Year

signs

Tritium 20 Year signs

Tritium 20 Year

signs

Tritium 20 Year

signs

Tritium 20 Year

signs

LCAAP

LCAAP

LCAAP

LCAAP

Building 3 Annex Exit Sign lsolite Tritium 11.5 Ci G SIN: Y66240 Model: 20 Year

.50cal PrimeILoad 2040 signs Lower level North

east door


.50cal PrimeILoad 2040 signs M e u level North

west door


.50cal PrimeILoad 2040 signs Mezz level North

double door


.50cal PrimeILoad 2040 signs Mezz level North

east door

4TTN:SJMLC-SF Independence.

MO

4TTN: S JM LC-SF Independence,

MO

ATTNISJMLC-SF Independence,

MO

ATTN :S J M LC-Sf Independence,

MO

NIA Y No

NIA Y No

NIA Y No

NIA Y No

Exit Sign Inventory (Containing Radiation)

10 year sign 7.5 Ci 20 year sign 11.5 Ci