ML20236L870

Amend 1 to License SNM-1591,amending License in Entirety

ML20236L870
Person / Time
Site:	07002166
Issue date:	08/12/1981
From:	Guinn P NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20236L784	List: ML20236L781 ML20236L818 ML20236L830 ML20236L844 ML20236L870 ML20236L890
References
NUDOCS 8708100385
Download: ML20236L870 (3)

Text

[/ .L . l d h i

• A/ ',

g g gg CATERS LS UCENSEU - Edh' *p> Amiendment h 01-y .

Pursuant to the Atomic Energy Act of 1954, as amendod, the Energy Reorganization- Act of 1974 (Public Law 93-438), and Title 10, Code of Federal Regulations, Chapter 1, Parts 30, 31, 32, 33, 34, 35, 36, 40 and 70, and in reliance on statements and representations heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, source, and special nuclear material designated below; to use such material for the purpose (s) and at the placels) designated below; to deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Partis); and to import such byproduct and source material. This license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified below.

Licensee In accordance with letter dated November 26, 1980

1. Inland Steel Mining C m Minorca Mine 3, License number StM-1591 is amended in its entirety to read as follows:

2. P. O. Box 1 ,

Virginia, Minnesota 55792 4. Expirat. ion date August 31, 1986 Docket or

5. Reference No. 070-02166

6. Byproduct, source, and/or 7. Chemical and/or physical 8. Maximum amount that licensee special nuclear material form may possess at any one time under this license A. Plutonium 238 A. Sealed sources (Custom A. One source of 0.5 gram Source - Texas Nuclear Model HMC-C-1049)

9. Authorized use l A. For use in Texas Nuclear Model NALA Analyzer for neutron activation Analysis.

CONDITIONS

10. Licensed material shall be used only at the licensee's facilities on U. S. Highway 53 North, Virginia, Minnesota.

11. 'Ihe licensee shall comply with the provisions of Title 10, Chapter 1, Code of Federal Regulations, Part 19, " Notices, Instructions and Reports to Workers; Inspections" and Part 20, " Standards' for Protection Against Radiation."

12. Licensed material shall be used by, or under the supervision of, Fred-L. keyeJM l fihusterickr or Charles W. Porter. i l

8708100385 861020 REG 3 LIC70 SNM-1974 PDR

]

t _ - _ - _ _ _ _ _ _ _

pq W $J.~&- ' h *$ h -$2;%$w.w Sm%% hh a u 3: LOR$N:ry& W a E,$ 35'

?~V' YnD

~ f,r.g:W 7:

5 2.Q;~

%yk s.

,, .' aU,' S. NUCLEAR' y u u- REGULATORY s wCOMMISSION "- N^g...M;U$,.

o X 'I ; ,_ ' # ;)

W i M7yg% 'N' g;',a , l t MATERIALS LICENSE ", ;n.mx' Licenk NumheF* B56-1981^

Q: ' < ,

s n . @,

.Supplememary Sheer; r: <

m

- _3 -;'

e .a a -

,p c" ~ > _. , ', ~

Douat or 5'

y1TIQE

~ , '

Refesuwe No. 070-02166 3

Amendment No. 01 (continued) .

M 13, Sealed sources containing licensed material shall not be opened or renoved fra the devices by the licensee.

14. A. (1) Each sealed source containing licensed material, other than Hydrogen 3, with a half-life greater than thirty days and in any fono other than gas a nhall be tested for leakage arm 5/or containution at intervals not to exceed six months. In the absence of a certificate fra a transferor indicating that a test has been made within six months prior to the transfer, a sealed source received fra another person shall not be put into use until tested. ,

(2) W e periodic leak test required by this condition does not apply to sealed sources that are stored and not beirs used. %e sources excepted frm this test shall be tested for leakage prior to any use or transfer to another person unless they have been leak tested within six months prior to the date of use or transfer.

B. %e test shall be capable of detectire the presence of 0.005 microcurie of radioactive material on the test sample. We test sample shall be taken fra the sealed source or fr a the surfaces of the device in which the sealed source is pennanently mounted or stored on which one might expect contamination to accumulate. Records of leak test results shall be kept in units of microcuries ard maintained for inspection by the Commission.

C. If the test reveals the presence of 0.005 microcurie or note of removable contamination, the licensee shall immediately withdraw the sealed source frm use and shall cause it to be decontaminated and repaired or to be disposed of in accordance with Cmmission regulations. A report shall be filed within 5 days of the test with the U. S. Nuclear Regulatory Cmmission, Region III, Office of Inspection and Enforcement, 799 Roosevelt Road, Glen Ellyn, Illinois 60137, describiry the equipent involved, the test results, and the corrective action taken.

D. Tests for leakage ard/or contamination shall be performed by the licensee or by other persons specifically authorized by the Commission or an Agreement State to perform such services.

e

l 4 mgg se sq, o ,

+

.. , ,,  ; s ; ..q. . n. , w.f . . cs.%. n . .. 2 .. l y , e

1. 4j. 7%  %'

3%ig 4

- l";"y ' g'..- ~;.3" Pages) e g", , , T., . . '1

/ .3,

' ;- +

' f i U. .S. NUCLEAR REGULATORY. COMMISSION 5'n A wir ' -

,x.

1591r7 ,. g MATERIALS LICENSE- ', ' License Num

,r Supplementary Sheet , Docket,or ,

00NDITICalS Reference No.070-02166 .

1 (continued) Amendment No. 01 I 15e me licensee shall conduct a physical inventory every six (6) months to account for all sealed sources received and possessed under the license.

We records of the inventories shall be maintained for two (2) yeare from the date of the inventory for inspection by the Connission, and shall include the quantities and kinds of byproduct material, location of sealed sources, and the date of the inventory.

16e Except as specifically provided otherwim by this license, the licensee shall possess and use licensed material described in Items 6, 7, and 8 of this license )

in accordance with statements, representations, and procedures contained in letter dated November 26, 1980; and application dated June 30, 1981. % e Nuclear Begulatory Cmmission's regulations shall govern the licensee's statenents in applications or letters, unless the statements are more restrictive than the regulations.

-N'121981 or the u. . . 'u . e 1 -

Commission

/

Material Licensing Branch t

Date by Dmaion of Fuel Cycle and

• Malenal Safety WanNngton, D.C. 20556 t _.

_ _ - - - _ _ _ - - - _ - ~

inWM] @eeFGinfng @mpny i

-.,--s.

Minorca Mine P.O. Box 1 - U.S. orth

• hg 4il DAvd 7f'7 - 2/4 I $

i Virginia, Minnuot 792 ggg (g .

218 749 5910 d.

gg k N lf Y w ,'

!* \q%\

M Inland Steel Mining 7

/

/\ '

June 30, 1981 f;

., '[IU Material Licensing Branch Division of Fuel Cycle and Material Safety Atten: Mr. Paul R. Guinn Office of Nuclear Material Safety and Safeguards Mh.97 Mail Control No. 17971 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:

Please find two (2) completed copies of NRC-3131 license renewel form pertaining to NRC license number SNM-1591. Please do not hesitate to contact ne if needing further assistance.

Sincer y,

( ,,

red L. Shu erich D. '

Senior P t Engineer

'd Inland Steel Mining Company Minorca Mine .,

1 C

~;.o

Enclosures:

Completed duplicate NRC-3131 l FLS:jmk e.

1 g ~,-

-91090~'M4 8106'30 \ s' PDR ADOCK 07002166 \

C PDR

', .[ ,

{

, s.

FORM NRC-313 l . U.S. NUCLEAR REOULATORY COMMISSION 1. APPLICATION FOR:

(3-80) (Check and/or complete as appropriate) 10 CF R 3D _

APPLICATION FOR BYPRODUCT MATERIAL LICENSE

a. NEW LICENSE INDUSTRIAL Soe sttached instructions for details. b. AMENDMENT TO:

LICENSE NUMBER Completed applications are filed in duplicate with the Division of fuel Cycle and Material Safety, Office of Nuclear Material Safety, and Safeguards, U.S. Nuclear Regulatory Commission'

c. RENEWAL OF*

Washington, DC 20555 or applications inay be filed in person at the Commission's office at g,ggn, gnu,jggg I117 H Street, NW, Washington. D. C. or 7915 Easterr' Avenue, Silver Spring Maryland. E SNM-1591 y 2. APPLICANT'S NAME (Institution, firm, person, etc./ 3. N AME AND TITLE OF PERSON TO BE CONTACTED REGARDING THIS APPLICATION Inland Steel Mining Company Fred L. Shusterich, Sr. Plant Engineer TELEPHONE NUMBER: ARE A CODE - NUMBER EXTENSION TELEPHONE NUMBER: ARE A CODE - NUMBER EXTENSION 218 - 749 - 5910 218 - 749 - 5910 X-66

4. APPLICANT'S MAILING ADDRESS (Include Esp Code / 5. STREET ADDRESS WHERE LICENSED MATERIAL VvlLL dE USED (Include Zip Code / *

(Address to which NRC correspondence, notices, bulletins, etc.,

should be sent./ Minorca Plantsite Laboratory P. O. Box 1 U. S. Hwy. 53 North, P. O. Box 1 Virginia, Minnesota 55792 Virginia, Minnesota 55792 (IF MORE SPACE IS NEEDED FOR ANY ITEM. USE ADDITIONAL PROPERLY KEYED PAGES.)

6. INDIVIDUAL (S) WHO WILL USE OR DIRECTLY SUPERVISE THE USE OF LICENSED MATERIAL (See items 16 and 17 for required traming and experience of each indivxtualnamed below)

FUL L NAME TITLE

a. Fred L. Shusterich Sr. Plant Engineer b,

c.

1. RADIATION PROTECTION OFFlCER Attach a resume of person's training and experience as outhned m items 16 and 17 and describe his responsibihties under item 15.

Charles W. Porter l

8. LICENSED MATERIAL CHEMICAL NAME OF MANUF ACTURER MAXIMUM NUMBER OF L ELEMENT AND AND/OR AND MILLICURIES AND/OR SEALED i

N MASS NUMBER PHYSICAL FORM MODEL NUMBER SOURCES AND MAXIMUM ACTI.

(t/ Scaled Source / VITY PER SOURCE WHICH WILL f.

BE POSSESSED AT ANY ONE TIME NO. A B C D Scaled Pu-Be Custom Monsanto Plutonium 238 Neutron Source Source 0.5 gram (2)

(

(3)

(4)

DESCRIBE USE OF LICENSED MATERIAL o E i

W Neutron Activation Silica Analvration (Custom Texas Nuclear NALA Analyzer)

(2)

(3)

(4) 9 ' "" -

F O RM N Pm*'C r" ' N 810630

• PDR ADOCK 07002166

_____-___c___ @@R

9. STORAGE OF SEALED SOURCES I

N

. CONTAINER AND/OR DEVICE IN WHICH EACH SEALED ~

SOURCE WILL BE STORED OR USED, NAME OF MANUFACTURER MODEL NUMBER

)

NO. A, B. C. -l gg3 Custom Monsanto Source. 3 phase Shieldinn-1. 12" X 12" lead evlinder Monsanto cunenm

2. 24" Borated WEP l (2)

3. 48" Water Jatknt l l

(3) j (4) ,

10. RADIATION DETECTION INSTRUMENTS TYPE M ANUF ACTU R E R'S MODEL NUMBER RADIATION SENSITIVITY OF NAME NUMBER AVAILABLE DETECTED RANGE Y (alpha, beta, (milliroentgen / hour N INSTRUMENT E gamme, neutron) or counts / minute) n, F A B C D E Geiger 2650 Alpha, Beta

$13 Counter Texas Nuclear Survey Instr . 1 Gamma 100 millirens/hr.

(2)

(3)

(4)

11. CALIBRATION OF INSTRUMENTS LISTED IN ITEM 10 Da. CALIBRATED BY SERVICE COMPANY Ob. CAllBRATED BY APPLICANT A ttach a separate sheet describing method, frequency and standards NAME, ADDRESS, AND FREQUENCY Texas Nuc1 ear Diviaion Frequency: Frequency: 6 month Ramsey Engineering Co. biennally Method: Calibration Standards Austin. Texas 78766

12. PERSONNEL MONITORING DEVICES (Check and/or compt to as appropriate.) (Serv ce C any)

A B O MONTHLY

[X(1) FILM BADGE O (2) THE RMOLUMINESCENCE R. S. Landauer, Jr. & Co. O QUARTERLY DOSIMETER (TLD) Glenwood Science Park O (3) OTHE R (Specsfy): Glenwood, Illinois 60425 Ki OTHER (Spec #fy):

every 2 weeks

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

O a. LABORATORY F ACILITIES, PLANT F ACILITIES, FUME HOODS (include filtration, if any), ETC.

(.

! O b. STOR AGE F ACILITIES. CONTAINERS,SPECIAL SHIELDING (fixed and/or temporary), ETC.

O c. REMOTE HANDLING TOOLS OR EQUIPMENT, ETC, O rt RESPIRATORY PROTECTIVE EQUIPMENT, ETC. N. A.

14. WASTE DISPOSAL

a. NAME OF COMMERCI AL WASTE DISPOSAL SERVICE EMPLOYED N. A.

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

Scaled source to be handled by manufacturer and returned to same.

FORM NRC 3131 (3-80)

. E ,

INFORMATION REQUIRED FOR ITEMS 15,16 AND 17 Describe in detail the information required for items 15,16 and 17. Begin each item on a separate page and key to the application as follows:

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

l

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

e. Principles and. practices of radiation protection.

b. Radioactivity measurement standardization and monitoring techniques and instruments.

c. Mathematics and calculations basic to the use and nyeasurement of radioactivity.

d. Biological effects of radiation.

17. EXPERIENCE. Attach a resume for each individual named in items 6 and 7. Describe individual's work experience with radiation, including where experience was obtained. Work experience or on-the-job training should be commensurate with the pre. posed use. include list of radioisotopes and maximum activity of each used.

18. CERTIFICATE (This item must be completed by applicant) w~

The applicant and any official executing this certificate on behalf of the applicant named in item 2, certify that this application is prepared in conformity with htle 10, Code of Federal Regulations, Part 30, and that all inform.otion contained herein, including any supplements artached hereto, is true and correct to the best of our know} edge and belief.

WARNING.-18 U.S.C., Section 1001: Act of June 25,1948; 62 Stat. 749: makes it e criminal offense to make a willfully falso statement or representation to any department of egency of the United States as to any matter within its jurisdiction.

A A

a. LICENSE FEE REQUIRED b. CERT -Y FICIA f ignaturp/ f (See Section 170.31,10 CFR 170) -

/ ,

j ~

, q: NAMd (Type d print)l

!/ i Freg L. Shusterich Previously Submitted I (1) UCENSE FEE CATEGORY: rC2 Senior Plant Engineer e.DATE (2) LICENSE FEE ENCLOSED: $

June 30, 1981 FORM NRc.313 t (3 80) gpo g g

l' l

l ITEM 15:

The radiation protection officer is , responsible for all plant site operations involving radioisotopes; nuclear detection sources.

Personnel coming in contact with the Custom Texas Nuclear NALA Analyzer are required to wear on their person film badge radiation detection devices.

The film badges are analyzed for radiation contam-ination every two (2) weeks by R. S. Landauer, Jr.

& Company, Glenwood, Illinois, 60425. NALA source leak tests are performed by Inland Sttel Mining Engineering biannually. Leak test kits are supplied and analyzed by Texas Nuclear Division, Ramsey Engineering Company, Austin, Texas, 78766.

J

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ i

J^

~

(s) .

. c)

%s s

ITEMS 16 6 17:

Charles W. Porter, Radiation Protection Officer:

The radiation protection officer is responsible for all plant site operations involving radioisotopes; nuclear detection sources. His formal training is attendance at the Texas Nuclear Radiation Safety Training School, Austin, Texas. Mr. Porter has served in the capacity of Radiation Protection Officer for Inland Steel Mining since 1961,.at which time he was located et Inland's Black River Falls, Wisconsin, operation. Mr. Porter presently serves as General Foreman, Electrical Department, Inland Steel Mining.

Fred L. Shusterich, Certifying Official:

Mr. Shusterich has been involved with neutron activation analyzers (NALA devices) for the past four (4) years. He holds a Bachelor of Science Degree in chemistry / biology from the University of Minnesota. Mr. Shusterich presently serves as Senior Plant Engineer, Operations, Inland Steel Mining Company.

l f

1 I

!