ML20198E022

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Matls Licensing Package for Amend 12 to License SNM-0192 for Univ of Michigan.Control:393566
ML20198E022
Person / Time
Site: 07000192
Issue date: 10/05/1992
From: Kevin Null
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
References
393566, NUDOCS 9212030343
Download: ML20198E022 (16)


Text

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SUPPLEMENTARY SHEET 070-00192 H{

Amendment No. 12 i  ?'$&h b h

i i University of Michigan h

! Radiation Control Service h

! 1077 North University Building W j Ann Arbor, MI 48109

{ ef In accordance with letter dated June 9,1992, license Number SNM-179 is amended as~~

{n follows: h[

Subitem 1. of Items 6.,

7. and 8 g% b ed c-rkd Items 6. , 7. , 8. and 9. are .am$1 d to add: i

)* 6. Byproduct, source

+%N. Chemical and/or < :.8.

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{ 9. Authorized Use:

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4 X. To be used as described in, and in accordance with, letter dated June 9,1992. d

'j Conditions 10.,11. and 16. are amended to read: y

10. Licensed material shall be used only at the licensee's facilities located at Cooley pl l4 Building /156 Measurements Laboratory; the Naval Architecture & Marine Engineering Building /120 Accelerator Bay; Phoenix Memorial Laboratory /1059 Research Laboratory &

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1069D Secured Storage; Ford Nuclear Reactor / Reactor Core Irradiation (NP-237 oxide fp1

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MATERIALS LICENSE >

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Amendment No. 12 s l l 4 >

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11. A. Licensed material shall be used by, or under the supervision of,

'1 Reed R. Burns, M.S., Ronald F. Fleming, Ph.D., Glenn F. Knoll, Ph.D., f

.] John King, Ph.D. , William R. Martin, Ph.D. , Michael J. . Longo, Ph.D. , or s

" Le Mark L. Driscoll, M.S. >

I B. Licensed material listed in Subitems 6.C. through 6.X. shall be used by, or g i under the supervision of Ronald F. Fleming, Ph.D., Reed R. Burns, M.S., ~~or p

,l Mark L. Driscoll, M.S. p

! 16. Except as specifically provid hhbi nh cense, the' licensee shall i

i conduct its program in a chi ce with the stateme representations, and ii procedures contained in e documents including any c esures, listed below. The 1 ,

Nuclear Regulatory Co@i sion's regulations shall gover)ngnless the statemen lg i representations and p g lq more restrictive than(ocedures the-regulations,in the licensee's applicat4on J and correspondence are 4

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Letters January datedlNay 28,.41988, Februa ,_1520,kly KDecember 4,198h, 1390fiAu 12, 1991, 41990, Sep)te h b

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Date /O[T-/@ By (.

Mater'Ials Licensing Section, Region III

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O  : INFORMATION FROM LTS EETWEEN:

LICENSE FEE MANAGEMENT ERANCH. ARM  : PROGRAM CODE: 22120 O AND . STATUS CODE: 0 REGIONAL LICENSING SECTIONS FEE CATEGORY: El 10 3M

EXP. DATE: 19930731
FEE COMMENTS: 170.11(A)(4)

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1. AFFLICATION ATTACHED O APFLICANT/ LICENSEE: MICHIGAN. UNIVERSITY OF RECEIVED DATE: 920608 DochET NO: 7000192 CCNTROL NO.. 393566 O LICENSE NO.: SNM-179 ACTION TYFE: AMENDMENT
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SENT BY: Olivetti FX 2100 43PM i 000VP SAFE ENV HLT 9170579055651# 2

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1205 N. UN:VIRSITY AVE.

1077 NORTH UNIVERSITY BU1LDING ANN ARBOR, M: 4a109-1057 i i

(313) 764 4310

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June 9, 1992 l

Mr. Kevin G. Null Materials Licensing section U.S. Nuclear Regulatory Commission, Region III  ?;,

799 Roosevelt Road Glen Ellyn, Illinois 60137 I 0,.

'o /, l ret Amendment to Special Nuclear Materials License SNM-179 _

, /

1 Dear Mr. Null!

The University of Michigan (U-M) is requesting amendments to the Nuclear Regulatory Commission - Special Nuclear Materials License SNM-179 as indicated below: 1 I 1.0 SNM-179 Docket Reference No. 070-00192  !

i 1.1 Amand Items 6(I), 7(I), and 8(I) to readt Byproduct, Source,and/or SNM: Neptunium-7.57 Chemical and/or Physical Formt N e p t u t.8. u m Ox.\0e2 (NPO ) ; Scaled in Welded aluminttn, I i stainless stes t , l titaniua or vanadium capsules-Maximum Possession Amount: 5 grams

, 1.2 Amend Items 6(X), 7(X), and 8(X) and add line. "X" Byproduct, Source, and/or SNMt I Depleted Urandum -'

%. _ ..s chemical and/or Physical Form Oxide or Metallic Activation Foils and Wires haximum Possession Limit: 5 grams RECEIVED RECCIVE av trMs a JUN O 81992

t , REGION III  !
,, Com0L E 93566

SENT BY: Olivetti FX 2100 9170679056651# 3 Q8-9213:43PMiOCCUPSAFEENVHL}"]

v Page 2 2.0 Amend condition 10 to read

" Licensed material shall be used only at licensee 8s facilities located at Cooley Building /156 Measurements Labcratory; the Naval Architecture & Marine Engineering Bu11 ding /120 Accelerator Bay; Phoenix Memorial Laboratory /1059 Research Laboratory & 1069D Secured storage; Ford Nuclear Reactor / Reactor Core Irradiation (NP-237 oxide sealed in welded aluminum, stainless steel, titanium, ter vanadium capsules; target foils, fission chambers, activation foils, and wires); and, t.he Dennison Building /337 Physics Measurements Laboratory."

3.0 Description of Materials The Np-237 will be provided to the FNR in the form of Npo, sealed in welded aluminum, stainless steel, titanium, or vanadium capsules by the Department of Energy (DOE) or other i licensed entities. Each capsule will have up to approximately 10 milligrams of Npo 2' While in the possession of the Ford Nuclear Reactor (FNR),

unirradiated Npo, dosimeter capsulca will be locked / secured in the Phoenix Memorial Laboratory (PML) radioactive material storage cage (Rm 1069D) until irradiation. The irradiated NpO2 capsules will be stored temporarily in the FNR pool or returned to the FML storage cage until they are shipped to the analyses, and DOE or other disposal. licensedoffacility The integrity the Npoforencapsulat counting, ion will not be breached while in the possession o,f the U-M.

/ The depleted uranium (Line X) will be provided by the DOE, other licensed facilities, or commercial vendors and stored in the limited-access FNR Facility or in the PML radioactive ,

material storage cage (Rm 1069D) until required for j/

irradiation. Following irradiation, the depleted uranium will be stored in the FNR pool or the PML radioactive material storage licensed other cage (Rm 1069D)itiesuntil facil fortheycounting, are shippedanalyses, to the DOEand or disposal. Individual dosimater foils or wires of depleted uranium will be limited to a mass of 50 milligrams.

4.0 General Information 4

Materials C through X are to be used under the supervision of Ronald F. Fleming, Ph.D., Reed R. Burn, M.S., or Mark L.

Driscoll, M.S.

GUEW 93566

1 SENT BY: Olivetti FX 2100 A 92 I 3:44PH I OCCUP SAFE ENV HL7 917087905665 # 4 V . . t l

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Page 3 In addition, please note that radiological safety and health  !

physics coverage will be provided by a full-time Radiation '

Safety Service (RSS) health physicist and all personnel exposures will be maintained ALARA.

i Please note that the U-M is requesting an expeditious reply to this SNM-179 amendment request - due to an immediate need. by the Ford Nuclear Reactor (FNR) staff to initiate this work. Please note

, that the FNR is increasingly being utilized as the irradiation site for neutron irradiation damage studies in support of programs such as the U.S. Nuclear Regulatory Commission Heavy Section Steel Irradiation (HSSI) Program.

! Adequate neutron dose monitoring of test specimens being irradiated will require greater use of Np-237 and depleted uranium dosimeters.

The U-M is requesting an increase in the maximum possession amount for Np-237 from the current 20 milligrams to 5 grams with respect to Line I and adding Line X (doploted uranium) because of increased need for these type of dosimeters. Note that the U-M is requesting a modification to the encapsulation requirements for the NP-237 (Line I) to better accommodate the needs for various experimental designs.

Thank you for your time, effort, and immediate attention to this SNM-179 amendment request. Your expeditious approval will be greatly appreciated by the staffs at the Ford Nuclear Reactor and

) Department of Energy. Please do not hesitate to contact the PNR Assistant Manager, Philip Simpson, at the PMh/FNR Facility ((313) 764-6220) or me at Radiation Safety Service ((313) 764-4420)-should you have any questions, comments, or concerns regarding this amendment request or correspondence, t

Sincerely,

(

d-Mark L. Driscoll

. Director / Radiation Safety Officer Radiation Safety Sarvice MLD/mid SNM179A cc: Reed R. Burn, Manager, Nuclear Reactor Laboratory James E. Carey, Chairman, Radiation Policy Committee Ronald F. Fleming, Director, Michigan Mozorial Phoenix Project Alan M. Jackson, Health Physicist, Radiation Safety Service Kenneth C. Schatzlo, Director, OSEH I Philip A. Simpson, Assistant Manager, Nuclear Reactor Lab 1

30L E 93566 i

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I IC77 NORTH UNIV [R$17Y BUILOtNC ANN ARDOR, MI 45109 1037 aterr senArns

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.....s OCT 0 61E TO THE LICENSEE:

Enclosed is the NRC license or license amendment which you requested. .

You are encouraged to carefully review your license or amendment upon receipt as special conditions may have been added to ensure that the changes requested meet NRC requirements.

Any future correspondence relating to your license should specifically reference your license number to expedite your inquiry.

Should you have any questions regarding your new license or amendment or require clarification, please contact the Materials Licensing Section at (708) 790-5625.

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Materials Licensing Section

Enclosures:

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$Ahe".mhieMEi + W d Y dfaw OCCUPATIONAL 5AFETY AND ENVIRONMENTAL HEALTH

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-(313) 764-8310 u%tft WHAfht t

l September 14, 1992

Mr. Kevin G. Null Materials Licensing Section U.S. Nuclear Regulatory Commission, Region III

, 799 Roosevelt Road Glen Ellyn, Illinois 60137

RE
Amendment to SNM-179 / Additional Information Requested

, [ Control Number 93566]

~

Dear Mr. Null:

! Per your request on August 11, =1992, please find attached a correspondence from PML/FNR Assistant Laboratory Manager Philip 4 Simpson addressing _ your concerns regarding the activation products produced by the encapsulation material-surrounding the neptunium oxide" and' depleted uranium sources to be irradiated- in the University of Michigan - Ford Nuclear Reactor. In addition, please note that Mr. Simpson has described briefly the radiological safety techniques that-will be employed when handling these irradiated materials.

! Thank you for your time, effort, and . consideration in this amendment. request. _ I hope this correspondence adequately addresses

the topics discussed during our August lith telephone . conversation.

Please do not hesitate to _ contact Phil Simpson at the PML/FNR

! Facility [(313) 764-6220] or D3 at Radiation Safety Service. [(313) 764-4420] should you-have any additional questions, comments, or concerns regarding this SNM-179 amendment request.

Sincerely Y. 0M Gu Mark L. Driscoll RECEIVED Director / Radiation Safety Officer Radiation Safety Service gEp 171992

[SNM179B] -REGION III cc: Reed R. Burn,_ Manager, Nuclear _ Reactor Laboratory James E. Carey, Chairman, Radiation Policy Committee Ronald F. Fleming, Director, Michigan Memorial- Phoenix Project.

Alan.M. Jackson, Health Physicist, Radiation. Safety _' Service Philip A. Simpson, Assistant Manager, Nuclear Reactor Lab

'l. ,

The. University of Michigan Michigari Memorial Phoenix. Project i Phoenix Memorial Laboratory  :,

, Ford Nuclear Reactor 2301 Honisteel Boulevard i Ann Arbor, Michigan 48109-2100 1 Tel. 313-7M-6220 4

. Mr. Kevin G. Null Materials Licensing Section

U.S. Nuclear Regulatory Commission, Region 111 799 Roosevelt Road

=

Glen Ellen, Illinois 60137

September 11,1992 i

l RE: Request for Further Infomiation Regarding Amendment to Special Nuclear Materials j License SNM 179 submitted 6/9/92.

j

Dear Mr. Null:

j The following are estimated activities for the various Np-237 encapsulation materials i requested in item 7(1). The estimates are based on a 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> irradiation followed by 30 1

days decay in the reactor pool prior to handling for shipment.

1-Aluminum encapsulation: No significant long lived activity The primary activation products are Al-28 ( Tu2 = 2.24 m ), Mg-27 ( T ie= 9.45 m ), and Na-24

( T ic= 15.02 h ).

l

{. Titanium encapsulation: 1.0 pCi Sc-46 (Ti c= 83.8 d ) ar..! 0.15 pCi Ca-45 (Tu2= 163 d).

Other activation products are relatively short lived; Ti-51 (Tl/2= 5.76 m ), Sc-47
(T ic= 3.41 d ), Se-48 (Tic = 43.7 h ), Sc-49 (Tv2=57.3 m ), and Sc- 50 j (Tv2= 1.71 m ).

i-i Vanadium encapsulation: No significant long lived activity. The primary activation products are V-52 (Tu2= 3.76 m ), Ti-51 (Tu2= 5.76 m ), Sc-48 (Tu2= 43.7 h ),

l and Sc-47 (TU2=3.41d).

L Stainless Steel encapsulation: 10 mci Cr-51 (T ta= 27.7 d),1.1 mci Fe-55 (Ti n= 2.73 y),

! 1 mci Co-58 (Tu2=70.9d),300 pCi Co-60 (Tv2=5.27 y). 200 itCi Mn-54

{ (T ic= 312 d),200 pCi Fe-59 (T ic= 44.5 d),80 pCi P-33.(T e= i 25.3 d), and .

i 20 pCi Ni-63 (T ic= 100 y).-

L As is readily apparent, the stainless steel encapsulation presents a significantly greater radiological hazard than the other encapsulation materials. We conservatively estimate the

, exposure rate from the stainless steel at one meter in air to be less than 20 mR/hr. It is our 5

intent to use aluminum, vanadium or titanium in preference to stainless steel encapsulation -

- whenever possible, f All radioactive materials are handled ALARA at the University. IThe Phoenix Memorial

, - Laboratory / Ford Nuclear Reactor (PMUFNR) has a full time independent Health Physics

- staff assigned by Radiation Safety Service who approve and monitor all transfers of the radioactive materials from the facility which will include the materials in this amendment -

request. All reactor facility personnel handling the materials will be full time staff members .

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u________ __ . _ _ __ _ _ _ _ . ,_ _

Page 2 September 11,1992 who have received training in and are knowledgeable about the handling of radioactive materials. Appropriate safety equipment such as lab coats, gloves, bootics, safety glasses, long reach handling tools, shieldmg, and minimization of handling time will be used as l needed to minimize personnel exposure, in addition, the PML/FNR has a fonnal daily contamination smear survey program to detect and eliminate radioactive contamination.

The survey program includes all areas where the materials requested in this amendment will be handled.

Sincerely, f

Phil M. Simpson Assistant 12boratory Manager 1

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O visit O CONftRtwCt 1 isttPr.ON O suc0Miho X Outoolmo hAr.t Of PER$m(S) CONTACTED OR IN CONTACT ORGANilAll0N (OfflCE, DtP1. tic.) ' TELEPHONE WO.

Mark Driscoll Univ. of Mich.

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C/N 93566

$UMMARY Regarding your request to perform neutron activation analysis of Hp-237 encapsulated in stainless steel, please-describe leak-testing procedures uted following activation to detect activation products from the steel encapsulation. Also describe precautiolea that will be followed during the leak test procedure, e.g., gloves and leo coats worn, personnel Lonitoring, etc. -

AcilON MQUIRED Respond within 10 days, in writing.

E ., PER$0N DOCUMENIlWG CONVER$All0N

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1077 NORTH UNIYlR$11Y ltUllDING ANN ARllOR, MI 46:09 1057 013) 764 8310 Hwin ( 9entnt June 9, 1992 Mr. Kevin G. Null Materials Licensing Section U.S. Nuclear Regulatory Commission, Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 RE: Amendment to Special Nuclear Materials License SNM-179

Dear Mr. Null:

The University of Michigan (U-M) is requesting amendments to the Nuclear Regulatory Commission - Special Nuclear Materials License SNM-179 as indicated below:

1.0 SNM-179 Docket Reference No. 070-00192 1.1 Amend Items 6(I), 7(I), and 8(I) to read:

Byproduct, Source,and/or SNM: Neptunium-237 Chemical and/or Physical Form: Neptunium Oxide (NPO2 ) ; ISealeds in welded aluminum, stainless steel, i

titanium or vanadium capsules Maximum Possession Amount: 5 grams l

1.2 Amend Items 6(X), 7(X), and 8(X) and add line "X" l

Byproduct, source, and/or SNM: s._ Depleted Uranium "~

l l

Chemical and/or Physical Form: Oxide or Metallic Activation Foils and Wires Maximum Possession Limit: 5 grams b

RECEIVED JUN11 1992 REGION III

[en

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O Page 2 2.0 Amand condition 10 to read:

" Licensed material shall be used only at licensee's facilities located at cooley Building /156 Measurements Laboratory; the Naval Architectitre & Marine Engineering Building /120 Accelerator Bay; Phoenix Memorial Laboratory /1059 Research Laboratory & 10cSD Secured Storage; Ford Nuclear Reactor /lsoMtor Fore Irradiation (NP-237 oxide scaled in welded a2 Winun, stainless steel,titsnium, or vanadium capsules; target foils, fission chambers, activation foils, and wires); and, the Dennison Building /337 Physics Measurements Laboratory."

3.0 Description et Materials The Np-237 will be provided to the FNR in the form of Npo, sealed -in welded aluminum, stainless steel, titanium, or vanadium capsules by the Department of Energy (DOE) or other licensed entities. Each capsule will have up to approximately 10 milligrams of NpO 2' While in the possession of the Ford Nuclear Reactor (FNR), ,-

unirradiated NpO2 dosimeter capsules will be locked / secured in '

the Phoenix Memorial Laboratory (PML) radioactive material storage cage (Rm 1069D) until irradiation. The irradiated NpO 2 capsules will be stored temporarily in the FNR pool or ',

returned to the PML storage cage until they are shipped to the DOE or other licensed facility for counting, analyses,_and disposal. The integrity of the NpO encapsulation will not be /

2 breached while in the possession of the U-M.

The depleted uranium (Line X) will be _provided. by the DOE, othc:r licensed facilities, or commercial vendors and stored ine the limited-access FNR Facility or in the PML radioactive material storage cage (Rm 1069D) until required for irradiation. Following irradiation, the depleted uranium will be stored in the FNR pool or the PML radioactive material storage cage (Rm 10690) until they are shipped to the DOE or other . licensed facilities for counting, analyses, and disposal. Individual dosimeter foils or wires of depleted uranium will be limited to a mass of 50 milligrars.

4.0 General Information Materials c through X are to be used under the supervision of Ronald F. Fleming, Ph.D., Reed R. Burn, M.S., or Mark L.

Driscoll, M.S.

fSTb[a i

o.. .

o Page 3 In addition, please note that radiological safety and health physics coverage will be provided by a full-time Radiation Safety Service (RSS) health physicist and all personnel exposures will be maintained ALARA.

Please note that the U-M is requesting an expeditious reply to this SNM-179 amt.ndment request due to an immediate need by the Ford Nuclear Reactor (FNR) staff to initiate this work. Please note that the FNR is increasingly being utilized as the irradiation site for neutron irradiation damage studios in support of programs such as the U.S. Nuclear Regulatory Commission Heavy Section Steel Irradiation (HSSI) Program.

Adequate neutron dose monitoring of test specimenu being irradiated will require greater use of Np-237 and depleted uranium dosimeters.

The U-M is requesting an increase in the maximum possession amount for Np-237 from the current 20 milligrams to 5 grams with respect to Line I and adding Linu X (depletsd uranium) because of increased need for these type of dosimeters. Note that the U-M is requesting a modification to the encapsulation requirements for the Np-237 (Line I) to better accommodate the needs for various experimental designs.

Thank you for your time, effort, and immediate attention to this SNM-179 amendment request. Your expeditious approval will be greatly appreciated by the staffs at the Ford Nuclear Reactor and Department of Energy. Please do not hesitate to contact the FNR Assistant Manager, Philip Simpson, at the PML/FNR Facility ((313) 764-6220) or me at Radiation Safety Service ((313) 764-4420] should you have any questions, comments, or concerns regarding this amendment request or correspondence.

Sincerely, dbd U Mark L. Driscoll Director / Radiation Safety Officer Radiation Safety Service MLD/mld SNM179A cc:- Reed R. Burn, Manager, Nuclear Reactor Laboratory Jamec E. Carey, Chairman, Radiation Policy Committee Ronald F. Fleming, Director, Michigan Memorial Phoenix Project Alan M. Jackson, Health Physicist, Radiation Safety Service Kenneth C. Schatzle,-Director, OSEH Philip A. Simpson, Assistant Manager, Nuclear Reactor Lab h b>

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