ML20210J128

Matls Licensing Package for Amend 21 to License SNM-111 for Department of Interior.Control:466449

ML20210J128
Person / Time
Site:	07000121
Issue date:	07/30/1997
From:	Campbell V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
References
466449, NUDOCS 9708150007
Download: ML20210J128 (19)

Text

,....,

u.s. NUCLEAR REGULATORY Commission Amendme t No. 21 MATERIALS LICENSE Pursu:nt to the Atomic Energy Act of 1954, as amended, the Energy Reorganizaton Act of 1974 (Puolic Law 93-438), and Title 10, Code of Federal Regulatons. Chapter I, Parts 30,31,32,33,34,35,39,40 and 70, and in reliance on statements and representations heretofore mida by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, source, tnd special nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated belov. to deliver or transfer such matenal to persons authonzed to receive it in accordance with the regulations of the applicable Part(s). This licer,2e shall be deemed to contain the conditons specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all app!icaok

.I rules, regulations and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any condrtions specified below.

Licensee in accordance with letter dated 1

June 20,1997

1. Department of the interior

3. License num:ser SNM-111 is amended in Geological Survey its entirety to read as follows:

2. P.O. Box 25046 M/S 205

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4,3 Expiration date December 31,2002 D:nver Federal Center

5. Docket Ho. 070-00121 Denver, Colorado 80225

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Reference No, t

6. Byproduct, source, and/or special,

7. Chemical and/or physical form 8." Maximum amount that licensee may nuclear material possess at any one time under this license A.

Any Special Nuclear Material Q X ny

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A, 7Not to exceed 105 times the g,)

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. applicable limits in Appendix I

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' Ej of 10 CFR Part 30 A

2 B.

Uranium-235 O

f,B Any f,. E f [J, B QO.0 grams C.

Uranium-233

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7 7 5 milligrams D.

Plutonium-236 1

An D ' 1.0 microgram 4'

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E.

Plutonium-239 E.

Any V

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2.0 milligrams h

F.

Plutonium-242 F.

Any F.

30.0 milligrams P

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9. Authorized use A. through F.

For use in research and development as defined in Section 70.4 of 10 CFR Part 70.

CONDITIONS

10. Licensed material may be used at Denver Federal Center, Denver, Colorado, and at temporary job sites of a

the licensee anywhere in the United States.

11, A.

Licensed material shall be used by, or under the supervision of, individuals designated by the U.S.

Department of interior's Radiation Safety Committee, Mr. Tim DeBey, Chairperson.

B.

The Radiation Safety Officer for this license is Darrell Liles.

9708150007 970730 PDR ADOCK 07000121 C

PDR OFFICIAL. RECORD COPY1 Am l!!ll!lll!ll ll!Ill!lli,llilll ML40 I

NRC Fo43m 374A' u.s. NuCLEAQ REoulATo2Y Commission PAGE 3 of - 3 PAGEs Lcense Number SNM-111 MATERIALS LICENSE Docket or Reference Number SUPPLEMENTARY SHEET 070-00121 Amendment No. 21

12. A.

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.

B.

Notwithstanding Paragraph A of this Condition, sealed sources designed to emit alpha particles shall be tested for leakage and/or contamination at intervals not to exceed 3 months.

C.

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.

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D.

Steled sources need not bileak tested if:

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(i) they contain only hydr. ogen-3; or Q (

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(ii) they contain only a radioactive gas; or

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r (iii) ine half-life of 'he isotope 30 ys

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(iv) they contain Et more

'm ries ta and/or, gamma mitting material or not more than 10 microcuries '

em materiai;,orf [

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p (v) they are not dSAlgned t -

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s, ptorage, and re not being used. However, when they are removed storage or transferred to another person, and have not been tested within the req' ired leak t'est lillsN,Til'1ey'sfNil be test'sd'before use or transfer. No u

f sealed source shall be stored for a period 5f more than 10, years without being tested for leakage and/or contamination, g

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fe E.

The leak iest shall be capable of detecting the ' presence of 0.005 microcurie of radioactive material on the test sample. If the test reveals the presence of 0.005 microcurie or more of removable contamination, a report shall be filed with the U.S. Nuclear Regulatory Commission in accordance with 10 CFR 30.50(b)(2), and the source shall be removed immediately from service and decontaminated, repaired, or disposed of in accordance w;th Commission regulations. The report shall be filed within 5 days of the date the leak test result is known with the U.S. Nuclear Regulatory Commission, Region IV, 611 Ryan Plaza Drive, Suite 400, Arlington, Texas 76011. ATTN: Director, Division of Radiation Safety and Safeguards. The report shall specify the source involved, the test results, and corrective action taken.

13. The licensee is authorized to transport licensed material only in accordance with the provisions of 10 CFR Part 71," Packaging and Transportation of Radioactive Material."

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

15. The licensee shall conduct a physical inventory every 6 months to account for all sources and/or devices received and nossessed under the license.

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NRC FORE 374A*

U.S. NUCLEAR REGulATo'.Y Commission PAGE 3 of 3 PAGEs Licmac Number SNM-111 MATERIALS LICENSE Docket r Reference Number SUPPLEMENTARY SHEET 070-00121 Amendment No. 21

16. In addition to the possession limits in bm 8, the licensee shall further restrict the possession of unsealed licensed material to quantities less thari 10 times the applicable limits in Appendix B of 10 CFR Part 30 as 5

specified in 10 CFR 70.25(d).

17, Except as specifically provided otherwise in this license, t**e licensee shall conduct its program in accordance with the statements, representations, and procedures contained in the documents, including any enclosures, listed below. The U.S. Nuclear, Regulatory.sCommission's regulations shall govern unless the statements, representations, and procedures in the licensee's application and correspondence are more restrictive than the regulations.9 '

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A.

Letter dated May 2,1989I

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B.

Letter dated February 4,'1992 "13 C.

Letter dated December 1,1992 D.

Letter dated April 30,.1993NN f,

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Letter dated June 15,1994 Y A(,

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Letter dated February 15,1995b

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Letter dated December 13,1994 3.

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Letter dated June 27,1995 3

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Letter dated August'10,199Qgyy

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Letter dated September 1

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Letter dated June 20,1997 5

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n 7 my u FOR THE U.S. NUCLEAR REGULATORY COMMISSION

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JUL 3 01997 d-

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D:te By (/NtA /

Gt 34 Vivian H.'C'ampbell /

Nuclear Materials Licensing Branch Region IV Arlington, Texas 76011 l

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NUCLEAR REGULATORY COMMISSION

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611 RYAN PLAZA DRIVE, SUITE 400 9*****

,o AR LINGTON, TEXAS 760118064 July 30,1997 U.S. Department of the Interior U.S. Geological Survey ATTN: Dr. Robert Zielinski Box 25046, M.S. 973 Denver Federal Center Denver, Colorado 80225-0046

SUBJECT:

LICENSE AMENDMENT Please find enclosed License No. 05-01399-08 and License No SNM 111. You should review this license carefully and be sure that you understand all conditions. If you have any questions, you may contact the reviewer who signed your license at 817-860-8143.

l:

L NRC expects licensees to conduct their programs with meticulous attention to detail and a high l

standard of compliance. Because of the serious consequences to employees and the public l

which can result from failure to comply with NRC requirements, you must conduct your program l

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.

U.S. Department of the Interior 6.

Maintain in a single document decommissioning records that have been certified for completeness and accuracy listing all the following items applicable to the license:

Onsite areas designated or formerly designated as restricted areas as defined in 10 CFR 20.3(a)(14) or 20.1003.

Onsite areas, other than restricted areas, where rr.dioactive materials in quantities greater than amounte listed in Appendix C to 10 CFR 20.1001-20.2401 have been used, possessed, or stored.

Onsite areas, other than restricted areas, where spills or other unusual occurrences involving the spread of contamination in and around the facility, equipment, or site have occurred that required reporting pursuant to 10 CFR l

30.50(b)(1) or (b)(4), including areas where subsequent cleanup procedures have removed the contamination.

scific locations and radionuclide contents of previous and current burial areas l

l n the site, excit. ding radioactive material with half-lives of 10 days or less, eted uranium used only for shielding or as penetrators in unused munitions,

...ealed sources authorized for use at temporary job sites.

Location and description of all contaminated equipment involved in licensed operations that is to remain onsite after license termination.

7.

Submit a complete renewal application with proper fee, or termination 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.

8.

Request termination of your license if you plan to permanently discontinue activities involving radioactive material.

s U.S. Department of the Interior 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; 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"(Enforcement Policy),60 FR 34381, June 30,1995.

Thank you for your cooperation.

Sincerely, Original Signed By Vuian H. Campbell I

l Vivian H. Campbell l

Senior Radiation Specialist Nuclear Materials Licensing Branch Docket: 030-03728/070-00121 License: 05-01399-08/SNM 111 Control: 466450/466449

Enclosures:

As stated

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JUL 3 01997 U.S. Department of the Interior l l

DOCUMENT NAME: P:\\

. To receivo copy of document, Indicate in box: "C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy RIV:NMLB RIV:

VHCampbell h

/\\ / % /9k 0FFICIAL RECORD LOPY a

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611 RYAN PLAZA DRfvE,sul1E 400

....*,0 ARLlNGToN, TEXAS 760118064 9-July 25,-1997 Department of the Interior ATTN: Dr. Robert Zielinski, Chairman Radiation Safety Committee Geological Survey Denver Federal Center P.O. Box 25046, M/S 205 Denver, Colorado 80225

SUBJECT:

- ACKNOWLEDGMENT OF REQUEST FOR LICENSING ACTION

REFERENCE:

LETTER DATED JUNE 20,1997 We have completed the administrative review and initial processing of your application.

During the initial processing, no omissions / deficiencies were identified. Please note that the technical review may identify additional omissions in the submitted information or technical issues that require additional information.

Amendment actions are normally processed within 60 days, unless the technical review identifies:

Major technical deficiencies Decommissioning / decontamination activities are required before an application can be completed Confirmatory closeout surveys after decontamination / decommissioning activities are required before a license can be terminated or a f acility removed from the license -

- Policy issues are identified that require input and coordination with other NRC Regional offices, Agreement State offices, or NRC's Office of Nuclear Materials and Safeguards A copy of your correspondence has been forwarded to our License Fee and Accounts Receivable Branch, Office of the Controller, who will contact you separately if the appropriate

. license fee has not been submitted for your request, or for billing if your request is subject to full cost recovery.

-)

Department of the Interior 2-Any correspondence about this application sh,nuld reference the Control number listed below.

Sincerely, b

Billie Gruszynski (Ms.)

Nuclear Materials Licensing Branch License: SNM 111 05-01399-08 Docket: 070-00121 030-03728 Control: 466449 466450 l

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Department of the Interior To receive a copy of this document, indicate in the box "C"

- Copy without attachment / enclosure "E" - Copy with attachment / enclosure "N" - No Copy OFFICE RIV:NMLB N

BGruszynski sk NAME.

DATE 7 /AI/97

Accrptanco Rcview Check List Action Type:

(gf) initiais or

( New

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Individuaim Amendment c mpleting

] Renewal Mail Control No.

Al4 d gq oate: WW/77 Administrative Exclusion items

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Requiring Return to Applicant:

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[]

Current Guidance Not Used

[]

References in Application Not to Current Regulations

[]

All Attachments Referenced Are Not included

[]

Signature Not on Application Technical Exclusion items Requiring Technical Reviewer Time Estimates:

[]

Request for Expedited Handling for Radiation Safety / Business Concerns l

[]

Request for Exemption to Specific Regulation (s) (cntered in LTS on by

)

[]

Change in Ownership Concerns i

[]

Financial Assurance /DFP Required

[]

Decommissioning Plan Review

[]

Quality Management Plan

[]

Termination of License Requiring NRC Closecut Survey

[]

Bankruptcy Notification

[]

Approval of Long Term Storage / Alternative Form of Waste Disposal

[]

Facility Modifications Requiring Shielding Calculations

[]

Authorization to Possess and Use Large Quantities of Unsealed Materials

[]

HDR/ Gamma Knife

[]

Major increase in Authorized Users

[]

Approval Of Training Program

[]

Approval of Incineration of Radioactive Waste

[]

Authorization For Sealed Source or Device Requiring SSD Approval Review

[]

Environmental Assessment or impact Statement Required

[]

Emergency Plan Contingency Plan Required

[]

Type A Broad Scope / Complex Research & Development Application Reviewer:

Estimate of Time Naeded:

[] 30 Days [] 60 Days [] 90 Days [] 180 Days [] Other Comments:

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United States Department of the Interior GEOLOGICAL SURVEY 4

BOX 25046 M.S._91.3.

I DENVER FEDERAL CENTER DENVER, COLORADO 80225 0046 h ut rt) killk 10 June 20, 1997 Re:

License No. 05-01399-08, Docket 030-03728 2

(License'NoU SNM-111R Dockets 070 001211 U.S. Nuclear Regulatory Commission, Region IV ATTN: Vivian Campbell, Health Physicist Nuclear Materials Licensing Section 611 Ryan Plaza Drive, Suite 400 3 0 !997 i;a y

Arlington, TX 76011-8064 l

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Dear Ms. Campbell:

Transmitted herein is a request for amendment of the two licenses referenced above.

The amendments involve the rotation of the Chairperson of the Radiation Safety Committee and the approval of a new Radiation Safety Officer.

i Item 1:

Proposed change of Chairperson, Radiation Safety l

Committee (RSC)

As the result of a ballot vote of the RSC, Mr. Tim DeBey was selected as Chairperson of the RSC.

The Chairperson position is filled for a nominal two year term by members of the RSC.

A resume of Mr. DeBey's training and experience is attached as enclosure 1 for your review.

Mr. DeBey will replace Dr. Robert Zielinski upon your approval.

Dr. Zielinski will continue to serve as a regular technical member of the RSC.

Item 2:

Proposed change of Radiation Safety Officer (RSO)

As the result of a ballot vote of the RSC, Mr. Darrell Liles was selected as the RSO.

I resume of Mr. Liles' training and experience is attached us' enclosure 2 for your review.

Mr.

Liles will replace Mr. William Andrle upon your approval.

Mr.

Andrle will continue employment with the USGS as the Central Region Safety Manager.

Due to restructuring of the USGS and the proposed RSO change, a new block dicgram for the administrative structure of the USGS Central Region Radiation Protection Program is also attached as enclosure 3 for your review.

If you have questions or require further information, you may contact me by telephone at (303) 236-4719.

Sincerely,

' V t

?V Dr. Robert Zielinski Chairman, Radiation Safety Committee 466449 9

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T RESUME dr. Tim DeBey TRIGA Reactor Supervisor U.S. Geological Survey P.O.

Box 25046, MS 974 Denver, CO 80225-O'046 (303) 236-4726 NUCLEAR-RELATED EDUCATIQH B.S.

Degree, Nuclear Engineering, Kansas State University, 1981.

M.S. Degree, Nuclear Engineering, Kansas State University, 1983.

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M.S. Thesis subject: Skin Dosimetry with Thermoluminescent Dosimeters.

(Received U.S.

Patent-No. 4,636,642 in 1987 for dosimeter design.)

, NUCLEAR-RELATED EXPERIENCE U.S. Navy NuclearTPower Program; Reactor Operator, Senior Reactor Operator and Reactor Operations Duty Section Leader, 1972-1978.

Kansas State University TRIGA Mk I Research Reactor; Reactor Operator, Senior Reactor Operator and Reactor Supervisor, 1978-1983.

Sandia National Laboratories; Reactor Operator, Reactor t

Supervisor, and Nuclear Systems Analyst, 1983-1988.

U.S. Geological Survey TRIGA Reactor Facility; Senior Reactor Operator, Reactor Supervisor, Authorized user under byproduct materials license, 1988-1995.

U.S. Army; Manager of the Army Reactor Office, Department of Army Headquarters, 1995-1997.

U.S. Geological Survey TRIGA Reactor Facility; Senior Reactor Operator, Reactor Supervisor, Authorized user under byproduct materials license, 4/97-present.

SAFETY-RELATED COMMITTEE MEMBERSHIP Kansas State University Reactor Safeguards Committee Sandia Pulsed Reactor Safety Committee - Secretary 1984-1985 USGS Reactor Operations Committee - Secretary 1989-1995 USGS Radiation Safety Committee - member 1989-1995, chair 1995 U.S. Army Reactor Council - Executive Secretary 1996-1997 USGS Radiation Safety Committee - member 5/97-present PROFESSIONAL SOCIETY MEMBERSHIP Alpha Nu Sigma (1983), KSU American Nuclear Society (1983-present)

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SPECIFIC RADIOLOGICAL TRAINING A.

Principles and practices of radiation protection:

a U.S. Navy Nuclear Power Program-Reactor Operator / Senior Reactor Operator Training-1972-1878 (OJT, instruction and certification).

b. Kansas State University (KSU)- Intro, to Nuclear Engg.-

3 credit hour course - 1978

c. KSU-Radiation Detection & Measurement-4 credit hrs-1980

d. KSU-Radiation Shielding-3 credit hrs-1982 B.

Radioactivity measurements, standardization, and monitoring techniques and instruments:

a. U.S. Navy Nuclear Power Program-Reactor Operator / Senior Reactor Operator Training-1972-1878 (OJT, instruction and certification).

b. KSU-Intro, to Nuclear Engg.- 3 credit hour course - 1978

c. KSU-Radiation Detection & Measurement-4 credit hrs-1980

d. KSU-Radiation Shielding-3 credit hrs-1982

e. KSU-Thesis Research and Training: TLD Dosimetry-1983 C.

Mathematics and calculations basic to the use and measurement of radioactivity:

a.

U.S. Navy Nuclear Power Program-Reactor Operator / Senior Reactor Operator Training-1972-1878

b. KSU-Intro, to Nuclear Engg.- 3 credit hour course - 1978

c. KSU-Radiation Detection & Measurement-4 credit hrs-1980

d. KSU-Radiation Shielding-3 credit hrs-1982 D.

Biological effects of radiation:

a.

KSU-Intro, to Nuclear Engg.- 3 credit hour course - 1978

b. KSU-Radiation Detection & Measurement-4 credit hrs-1980

c. KSU-Radiation Shielding--3 credit hrs-1982

d. KSU-Thesis Research and Training: TLD Dosimetry-1983 SPECIFIC RADIOLOGICAL EXPERIENCE (use of radioactive materials)

A.

Specific isotopes handled or used:

Uranium in reactor fuel; mixed fission products in spent fuel; activation and fission products with atomic numbers 3 to 83; Co-60 and Cs-137 irradiators; AmBe, PuBe and RaBe neutron sources.

B.

Maximum quantities of material handled or used:

Kilogram quantities of SNM as reactor fuel; hundreds of curies of reactor-contained products; up to 5 Ci total byproduct material in any form; up to a few curies each for sealed sources or special form materials.

C/D.

Location and duration of experience received:

U.S. Navy Nuclear Power Program - 6 years (1972-1978)

Kansas State University - 5 years (1978-1983)

Sandia National Laboratories - 5 years (1983-1988)

U.S. Geological Survey TRIGA reactor - 7 years (1988-1995)

E.

Type of use of radioactive materials:

Operation and maintenance of nuclear research reactors; reactor irradiations; material handling for research related to neutron activation analyses, isotope production, radiation effects, and dosimetry; and radiation instrument development, maintenance, and calibration.

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l PESUME Darrell Liles TRIGA Reactor Health Physicist US Geological Survey Denver, CO 80225 (303) 236-4726 NUCLEAR-RELATED EDUCATION 1996, B.S. Nuclear Engineering, University of Misecuri-Rolla (UMR)

NUCLEAR-RELATED EXPERIENCE US Navy Nuclear Power Program; Engineering Laboratory Technician / Mechanical Operator 1986 - 1992.

Nuclear Support Services; Senior Health Physics Technician 1992.

University of Missouri-Rolla; Health Physics Technician for RSO concerning Type A broad license activities 1994 - 1996.

U.S Geological Survey TRIGA Reactor Facility; Reactor Health Physicist and authorized user under Type A Broad Material License 1996 - present.

PROFESSIONAL SOCIETY MEMBERSHIP American Nuclear Society (1995 - present)

Tau Beta Pi (1993 - present), UMR Alpha Nu Sigma (1995-1996), UMR S

SPECIFIC RADIOLOGICAL TRAINING AND EXPERIENCE see attached (Yvisl,? ~)

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Darrell Liles - Specific Radiological Training and Experience TRAINING A. Principles and practices of radiation protection:

l US Navy Nuclear Power Program; Engineering Laboratory a.

Technician / Mechanical Operator 1986 - 1992.

b.

University of Missouri-Rolla

('UMR)

Nuclear Engineering - 3 credit hour course 1993. Introduction to i

I UMR - Interaction of Radiation with Matter - 3 credit hour c.

course 1994 d.

UMR - Nuclear Radiation Measurement - 3 credit hour co' rse 1995 u

i B. Radioactivity measurements, techniques and instruments: standardization, and monitoring 4

a. US Navy Nuclear Power Program; Engineering Laboratory Technician / Mechanical Operator 1986 - 1992.

b. UMR - Nuclear Radiation Measurement - 3 credit hour course 1995

c. UMR - Reactor Laboratory I - 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> class 1995

d. UMR - Reactor Laboratory II

e. UMR - Radioactive Waste Management-2 hour class 1996 1995

- 3 credit hour course C. Mathematics and calculations basic to the use and measurement radioactivity:

a. US Navy Nuclear Power Program; Engineering Laboratory Technician / Mechanical Operator 1986 - 1992.

b.

University of Missouri-Rolla (UMR)

Introduct.'on to Nuclear Engineering - 3 credit hour course 1993.

c. UMR - Interaction of Radiation with Matter - 3 credit hour course 1994 d UMR - Nuclear Radiation Measurement - 3 credit hour course 1995 D. Biological effects of radiation

a. US Navy Nuclear Power Program; Engineering Laboratory Technician / Mechanical Operatrr 1986 - 1992.

b.

UMR - Interaction of Radiation with Matter - 3 credit hour course 1994 UMR - Nuclear Radiation Measurement - 3 credit hour course c.

1995 EXPERIENCE A. Specific isotopes handled or used:

Co-60 and Cs-137 calibration sources; tritium, C-14, t

32; activation and fission products with atomic numbers 3 to S-35, P-837 PuSe neutron sources I

v 1

B. Maximum quantities of material handled or used up to few a curies each for the sealed sources; up to 5 curies for byproduct material, up to 5 curies each for tritium, P-32, S-35 and C-14, 1

C. Where and when experience gained:

US Navy Nuclear Power Program - 6 years (1986 - 1992)-

Nuclear Support. Services: refueling outage-- 3 months (1992)

University of Missouri-Rolla Nuclear Eng. Dept.

4 years (1992 - 1996)

UMR Occupational Health and Safety Office - 2 years (1994 1996)

US Geological _ Survey TRIGA Reactor Facility - 1 year (1996 -

present)

D.---Type of use:

Operation and maintenance of nuclear reactors and associated equipment; reactor-irradiations; radiation-instrument calibrations, radioactive waste handling; sealed source leak test; NRC Type A Broad Material License and Research Reactor License compliance.

DIRECTOR U.S. GEOLOGICAL SURVEY

CHIEF, CHIEF REGIONAL l

OFFICE OF GE014 GIST

DIRECTCR, l

PROGRAM SUPPORT CENTRAL REGION l

USGS REGIONAL RADIATION SAFETY MANAGER GEOLOGIST, SAFETY CENTRAL REGION COMMITTEE I

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CENTRAL REGION REGIONAL RADIATION SAFETY SAFETY MANAGER OFFICER Administrative Structure for the USGS Central Region Radiation Protection Program for the management of broad-scope license activities.

In the diagram, solid lines (-) represent normal reporting paths and flow of authority; asterisked lines (* * *)

represent direct lines of communcation and delegation of authority; and I

dotted lines (.

.)

represent paths of collaboration and advice regarding general safety management.

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