ML20211H022
| ML20211H022 | |
| Person / Time | |
|---|---|
| Site: | 07001374 |
| Issue date: | 09/30/1997 |
| From: | Kunze J IDAHO STATE UNIV., POCATELLO, ID |
| To: | Weber M NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML20046D838 | List: |
| References | |
| NUDOCS 9710060159 | |
| Download: ML20211H022 (12) | |
Text
0F qs-Ivf September 30, 1997 Mr. Michael F. Weber, Chief Licensing Dranch Division of Fuel Cycle Safety and Safeguards, IMSS U.
S. Nuclear Regulatory Commission Washington, D.C.
20555-0001 STX1'E Rei Docket No. 70-1374, License No. SNN-1373 UNIVERSITY
Dear 14r. Weber:
Enclosed are six copies of an applicaticn for renewal of the Idaho State University (ISU) license for Special Nuclear Material, as described.
The renewal request is for five (5) years and renewcl of license is for the original License No. Sim-1373, due to expire October 31, l OEr d the Dean 1997.
k The enclosed application has been prepared and is being ces Box smo submitted to you pursuant to Title 10, Code of Federal Pocateno. Idaho Regulations, Part 70, Section 70.33, using the format
! 8N8%0 previously submitted for our license.
(
Please note that we have removed from this license renewal application the 20 g of plutonium-239 in the form of sealed Pu-Be neutron sources, which are listed in the current version of License No. SNM-1373, because those materials are already licensed for use at ISU under U.S.
NRC Materials License No, 11-27380-01 (Docket No. 030-32322/IDA-33-1).
A copy of this license is enclosed for your review.
If you desire further information, please contact:
John S.
Bennion, Reactor Administrator College of Engineering Idaho State University ISU Box 8060 Pocatello, ID 83209 (208) 23G-2902 We would appreciate prompt action in this matter.
I 1
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- erely,
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Ja F. Kunze, Ph.D.,
P.E.,
CHP Dean and Professor JFK:ik lll$ l)lllf lllfl*ll
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Phone:
9710060159 970930 (208) 23& 2902 PDR ADOCK 07001374 fax:
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l IDAHO STATE UNIVERSITY COLLEGE OF ENGINEERING 1
l
SUBJECT:
Idaho State University desires renewal of Materials License No. SNM-1373, to possess and use the special nuclear material listed below:
l (1) 1510 gm of uranium-235 in the form of 150 l
uranium-aluminum fuel plates.
l (2) 1 gm of uranium-235 contained in 74 uranium-aluminum foils and 1 fission counter.
Please note that we have removed from this license renewal application 20 g of plutonium-239 in the l
form of sealed Pu-Be neutron sources, which are listed in the current version of License No. SNM-1373, because those materials are already licensed for use at ISU under O. S. NRC Materials License No. 11-27380-01 (Docket No. 030-32322/IDA-33-1).
A copy of this license is included as enclosure i
(1).
1 ENCLOSURES:
(1)
U.S. NRC Materials License No. 11-27380-01 L
(2)
Biographical Data for Operating Staff (3)
Water Handling System Diagram l
(4)
Water Handling System Electrical Diagram (5)
Criticality Monitor Specifications (6)
Basement Floor Building Plan (7)
Ground F1.oor Building Plan (8)
Idaho State University Map (9)
Pocatello Area Map
REFERENCES:
(1)
Rutgers University Special Nuclear Material l
License SNM-431, Docket Number 70-461.
l (2)
Idaho State University Application for 104 l
Construction Permit, Class 104 Facility License and By-products Materials License, i
April 3, 1967 License Number SOP-934-2, Docket Number 55-638, (3)
Emergency Plan for the Nuclear Facility at Idaho State University. (Rev. 5 94/26/94) l The College of Engineering at Idaho State University uses the subcritical assembly to strengthen the existing undergraduate and graduate programs in the area of nuclear science and engineering.
L The subcritical assembly was originally assembled and operated at Rutgers University, New Brunswick, New Jersey.
Information required by sections of 10 CFR 70 will be listed after the sequence number of the section in 10 CFR 70 requesting that information.
i l.
I
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pj -
4 Ft 37 APPLICATION FOR LICENSE RENEWAL MATERIALS LICENSE No. SNM-1373 70.22.1 Information about the applicant, his plans and qualification.
Name:
Idaho State University Addresst Pocatello, ID 83209 Description of Business or Occupation:
Institution of Higher Learning The Idaho State University (ISU) is operated by the State of Idaho with its principal office at Pocatello, Idaho. The Idaho State Board of Education (SBOE) provides oversight and direction of the higher education institutions in Idaho and is located in Boise,
- Idaho, (P.O. Box 83720-0037).
University of ficers cac c"trrently:
Dr. Richard L.
Bowen, President of the University Administration Building Idaho State University Dr. Jonathan N.
Lawson, Academic Vice President Administration Building Idaho State University Dr. Robert W.
Pearce, Financial Vice President Administration Building p
Idaho State University Dr. Jay F.
Kunze, Dean of the College of Engineering Lillibridge Engineering Laboratory Building Idaho State University Additionally, the Radiation Safety Officer for the University is:
Dr. Thomas F. Gesell Physical Science Building Idaho State University (All of the above board members and of ficers are citizens of the United States.
There is no control or ownership exercised over the applicant by any
- alien, foreign corporation, or foreign government.)
70.22.2a Activity for which the material is requested.
The material is requested for education and training programs.
A total mass of 1511 g of U-235 is requested in this application.
1510 g of U-235 are contained in 150 uranium-aluminum fuel plates.
The remaining U-235 being requested, rounded up to 1 g, will be contained in 1 fission counter and 74 uranium-aluminum foils.
(
l ISU College of Engineering 9/30/97
v s
The fuel plates will be loaded in var'.ous lattice arrangements in a water-filled tank to produce a suberitical assembly (SCA).
The fuel plates may be used singly for a quasi-homogeneous assembly or in groups of two or more to produce a heterogeneous configuration.
The uranium-aluminum foils will be used as neutron monitors in some experiments performed with the suberitien1 assembly.
The materials will be used primarily for instructional purposes in senior-and graduate-level laboratory courses.
In
- addition, research programa utilizing the materials in the suberitical i
assembly will also be encouraged.
No activity will be performed without the prior approval of the Reactor Administrator, a
Some of the experiments to be carried out with the suberitical assembly are:
(1)
Approach to critical.
i 1
(2)
Flux distribution measurements.
(3)
Exponential pile measurements.
(4)
Fermi age determination.
in a
(5)
Determination of optimal cell dimensions heterogeneous suberitical assembly.
(6)
Effect of fuel-plate thickness on multiplication factor.
(b ) The place and the general plan for carrying out the activity.
The material will be used and stored in Room 23 in the basement of the Li111 bridge Engineering Laboratory (LEL) Building at Idaho State university. Room 23 is 20-feet by 20-feet square with a 12-foot ceiling. The floor is a 4-inch-thick reinforced concrete slab.
The corcrete was poured over the undisturbed soil and reinforced with r.4 bar spaced 12 inches apart.
The floor will safely accommodate the weight of the entire SCA. Located in the same section of the basement is the Reactor Supervisor's office and the decontartination f acility.
Room 23 is a controlled access area.
only tha
- Dean, the Reactor Administrator, and the Reactor Superviser have keys to this section of the basement.
Other personnel, authorized by the Reactor Administrator, may have access to a key to Room 23 that is kept in a metal box secured with a combination lock.
I In addition, up to 10 fuel plates and/or up to 25 uranium-aluminum foils will be used occasionally at the ISU Accelerator Center as sources of fissile material for research into methods for the nondestructive assay and evaluation of fissile materials in transuranic waste drums and other closed containers.
In this
- capacity, the fuel plates and/or foils will be used at the Accelerator Facility during regular working hours only and will be stored in Room 23 of the LEL at all other times as stated above.
Materials will be transported between the LEL and the Accelerator Facility under the supervision of ISU Technical Safety Office personne) in accordance with applicable Federal,
- State, and University regulations.
Whenever materials are removed from Room 23 for use at the Accelerator Center, they will remain in the custody of the responsible user until returned to the approved storage container in Room 23.
2 ISU college of fingineering 900/97 i
4 70.22a(3) Period of time for license.
This license is requested for a period of 5 years.
It is expected that a request for renewal will be submitted at the end of that period.
70.22.a(4)
Specification of the special nuclear material.
l (a)
Uranium-aluminum fuel plates.
1 The fuel plates were f abricated in 1960 by M & C Nuclear, Inc., for Rutgers University, New Brunswick, New Jersey.
The manufacturer's specifications for the plates are as follows:
Total number of plates 150 Total mass of uranium 7614.79 g Enrichment of U-235 isotope 19.83%
Total U-235 content 1510.27 g 2
U-235 loading per plate 10.07 g overall dimensions of plate (2610.015 in) x (3.010.015 in)
Dimensions of uranium bearing portion of the plate (24 in x 2.75 in x 0.04-in)
Cladding thickness 0.020 in (b)
Fission counter and uranium-aluminum foils.
(i)
Fissior, counter.
Total uranium mass 0.002 g U-235 enrichment 93%
Total uranium mass 0.002 g (ii) Uranium-aluminum foils, a
Total number of plates 74 Total uranium mass 0.3 g U-235 enrichment 93%
Total uranium mass 0.3 g Specifications for the above items were taken from the U.S.
Atomic Energy Commission's Nuclear Material Transfer Report.
70.22.a.6 Technical qualifications of the applicant and staff.
Attached as enclosure (2) are the biographical data for those members of the Idaho State University faculty who will have
. responsibility for the supervision and operation of the SCA.
John S.
- Bennion,
'Ph.D.,
P.E.,
Assistant Professor of Engineering and Reactor Administrator.
3 ISU College of Engineering W30/97
4 Jay F. Kunze, Ph.D.,
P.E.,
CHP, Dean, College of Engineering, Professor of Engineering and Alternate Reactor Administrator.
- Thomas F.
- Gesell, Ph.D.,
Professor of Health Physics and Radiation Safety Officer.
70.22.a.7 Equipment and facilities to protect health and minimize danger to life and property.
(a)
Handling procedures.
(i)
Fuel plates.
l Disposable plastic gloves or other hand coverings will be used by personnel while handling the fuel plates.
(ii) Uranium-aluminum foils.
Tongs, disposable plastic gloves, or other hand coverings will be used by personnel while handling the foils.
(a)
Working area.
See. 70.22.a. 2.b: The place and plan for carrying out the activity.
(b)
Measuring and monitoring instruments.
Beta, gamma, and neutron dosimeters provided by an NVLAP-certified vendor are issued to all students and staf f working with the special nuclear material.
Electronic measuring equipment of the following generic characteristics will be available for use during SCA operations:
NaI(Tl) and HPGe gamma spectrometers.
Gas-flow 2-n proportional counter (Technical Associates Model SFM-SV-3, or equivalent).
Fast neutron detector (Health Physics Instruments Model Rem-500, or equivalent).
Hand-held servey instruments:
Ludlum Model 14A Geiger Counter with beta / gamma probe (or equivalent).
Ludlum Model 2A Geiger Counter with thin-window pancake probe (or equivalent).
Eberline Model E-120 Geiger Counter with beta / gamma probe (or equivalent).
Ludlum Model 3 Survey Meter with Zns alpha probe (or equivalent).
In addition, all available portable radiation monitoring equipment listed in the "By-products Materials License" (reference 2,' page 27, 4
ISU College of Engineering 9/30N7
e para. 9) may be used by College of Engineering personnel, if necessary.
(c)
Waste disposal.
There will be very little waste contaminated by radioactive materials resulting from the handling, storage, and use of materials under this license.
Contaminated material will be l
controlled and disposed of by ISU Technical Safety Of fice personnel in accordance with written procedures.
(d)
Storage facilities and security measures.
There is a minimum of two locked doors which will prevent I
unauthorized access to the special nuclear material.
When the SCA is not in operation, the uranium-aluminum fuel plates will be secured in their shipping container.
The shipping container will be located in Room 23.
The fuel plates may be stored in either the assembly tank or the shipping container.
Both the assembly tank and the shipping container will be locked when containing the fuel plates.
The uranium-aluminum foils will be stored with the fuel plates in Room 23 in either the assembly tank or_the shipping container.
The fission J
counter will be stored in Room 20, in which the AGN-201 nuclear reactor is located.
All entrances to the LEL building are secured from approximately 10:00 p.m.
to 6:30 a.m. on weekdays and remain locked on weekends and holidays.
In addition, the building is patrolled by officers of the ISU Public Safety Department several times daily at random hours between 4 :00 p.m. and 8:00 a.m.
(e)
Water handling system.
Deionized water will be used as the moderating medium in the SCA.
The deionized water will be stored in three 53 gallon polyethylene drums.. The drums will be connected to each other by a 1/2-inch pipe in such a manner that water can flow freely between the tanks.
At the beginning of each experiment deionized water will be pumped from the storage tanks to fill the assembly tank.
At the end of each experiment the water will be drained out of the assembly tank through a 3/4-inch drain line near the bottom of the tank.
Alternatively, water may be pumped into the tank already loaded with the SCA lattice to measure the increase in neutron multiplication (k n) as a function of moderator height.
A schematic diagram of the water handling system is provided as enclosure (3).
The drain pipe will be opened and closed by a "normally opened" solenoid valvo.
In the event of a power failure, the pump will shut off-and the drain valve will open so_that any water in the tank will necessarily drain out of the _ assembly tank.
Without water acting as moderator the 5
isU college of lingineenng 9aom
)
neutron multiplication factor of the assembly will be extremely small.
Power feeding the solenoid drain valve and the pump will first go through a double-pole open solenoid switch.
This switch will be held open by the signal out of the criticality alarm.
In the event of an inadvertent criticality (an extremely improbable event),
or a high i
radiation alarm (>5 mrem /hr), power will be automatically cut of f to the pump and the solenoid drain valve, causing water to drain out of the assembly tank.
Further, the solenoid switch l
will be wired in such a manner that any attempt to disconnect t
the solenoid switch from the criticality alarm will result in loss of power to both the pump and the solenoid drain valve.
The wir:.ng diagram for this installation is provided as enclosure (4).
70.22.a.8 Proposed procedure to protect health and minimize danger to life and property.
(a)
Radiation hazard.
(i) -Radiation hazard -from subcritical assembly during operation.
Reference 1,
page 11, provides the information given below:
Direct Calculations BSF Data Fast neutrons 0.16 mrem /hr
<4.6 mrem /hr Thermal neutrons 0.21 mrem /hr Gamma photons 5.0 mrem /hr 2.6 mrem /hr These dose equivalent rates are not expected to constitute a hazard to personnel for the following reasons (1)- The dose equivalent rates listed above are given at the surface of the assembly tank; personnel are rarely that close to the assembly for any extended period.
(2)
Personnel will only spend a few hours a week in the vicinity of the SCA while it is operating.
(3)
Personnel are required to actively pursue the ALARA policy..
Operation of the SCA to date has not revealed any radiation hazard.to personnel.
However, a criticality alarm is installed in Room 23, as required by 10 CFR 70.24.-
Furthermore, all personnel involved in the operation-of the SCA shall wear ISU-issued personal dosimetry capable of measuring beta, gamma, and neutron dose equivalents.
Visitors will be issued self-reading pocket dosimeters while in Room 23.
In the event that 6
isu college or ringineering 90aw
[
.4 l
l the number of visitors exceeds the number of available self-reading pocket dosimeters, a minimum of I dosimeter will be issued for every 4 visitors, so that at least one-quarter of the visitors to the facility are monitored for exposure to ionizing radiation.
In addition to the l
fixed criticality alarm, a gamma detector will be in l
o?eration at all times that personnel are in Room 23 l
while fuel is located in the suberitical assembly tank.
(ii) Radiation hazard from neutron sources.
Two Pu-Be neutron sources will be used to provide neutrons for the operation of the SCA.
The dose rate at 3 feet from the strongest source is 2.2 mrem /hr. Neutron sources will be located in the graphite pedestal during SCA operation. Alternatively, the neutron sources may be placed in a moderating source holder near the bottom of the assembly tank.
The neutron sources will be stored in a paraf fin-lined storage container when not being used in the SCA.
Personnel will be handle the sources with tongs or source holders.
Such handling will be under the supervision of the Reactor Administrator, the Reactor Supervisor, or the Radiation Safety Officer.
(b)
Fire hazard.
No materials or chemicals will be stored in Room 23 which could present a fire hazard.
Normal fire rules will be observed.
There is a
dry-chemical, "ABC"-class fire extinguisher located next to the door of Room 23.
Two other fire extinguishers are located nearby in the same section of the basement.
A heat-rise sensor is located in the ceiling in Room 23 above the assembly tank.
Activation of the sensor by-y a fire will sound the building fire alarm and energize an indic;cor light on a fire location annunciator panel, which is located at the east main entrance.
In the event of a fire which may cause damage to the fuel plates or foils, a leak test will be performed on all fuel plates and foils.
(c)
Inadvertent criticality.
The SCA - has been designed to be suberitical under all conditions.
Operation has verifled the design calculations.
Criticality,
- however, may occut by the introduction of superior moderator or reflector materials to the assembly.
Therefore, the.following administrative control has been implemented to prevent-inadvertent criticality:
' NOTICE The f ollowing quantities-of specific materials are ng to be taken into the suberitical assembly area without the permission of the. Reactor Administrator: graphite
-8 lb, beryllium - 2 lb, beryllium oxide - 4 lb, heavy water - 2 lb, fissionable isotopes ( 3 "U.
- U,
'"Pu) 3 gm of any one isotope or combination of isotopes except for the Pu-Be sources necessary for facility operation. Permission will be granted for only one material at a time.
Ouantities cannot 7
ISU College of Engineering 9/30/97 l-
exceed the amounts soecified above.
These limitations apply to all chemical forms of, and mixtures containing, the above materials.
Detailed plans of the experiment to be conducted must be submitted before approval will be granted.'
A fixed ~ criticality alarm system is installed in Room 23. The alarm is manuf actured by the Ludlum Instrument Company, and fulfills the criticality alarm requirement stated in 10 CFR 70.24.
(d)
Personnel monitoring.
Personnel ptesent in Room 23 during operation of the SCA will wear personal dosimetry.
Staff and students will be issued beta, gamma, and neutron-sensitive dosimetry that will be processed by an INLAP-accredited laboratory. Visitors will be issued self-reading pocket dosimeters while in Room 23.
In the event that the number of visitors exceeds the number of available self-reading pocket - dosimeters, a minimum of 1 dosimeter will be issued for every 4 visitors.
411 personnel monitoring on campus is in accordance with 10 CFR 20 requirements and the ALARA philosophy is actively practiced.
(e)
Leakage testing and surveys.
Ten percent of the fuel plates will be leak tested using standard swipes for alpha contamination prior to each experiment and at normal inventories.
Ten percent of the uranium-aluminum foils will be tested in conjunction with the fuel plates.
For the purposes satisfying the requirements of this section, a leak test will be assumed to have been performed satisfactorily if the test was performed within a two week period prior to the commencement of the experiment.
A general area and contamination survey will be performed in conjunction with the leakage testing.
In addition, a monthly contamination survey and general radiation survey will be performed in Room 23.
Further, a water sample will analyzed annually for evidence of fuel leakage.
All materials used at the Accelerator Facility will be leak tested upon return to Room 23.
70.22.b (i) Inventory procedures.
Inventory of the material will be performed at least twice each year.
It is anticipated that all fuel plates will be t
used in any experiment conducted in Room 23.
This fact, and assembly procedures, will reveal any missing material.
An
~
approved emergency plan establishes procedures to be followed in the event of loss or theft of special nuclear material.
(Reference 3, page 17.)
Materials transferred to the Accelerator Center will be inventoried prior to removal of the materials from Room 23 and y
7 8
ISU Cci!ege of Engineering 9/3097
+5 w -
_~
1 again upon return of the materials to Room 23.
(ii) Administrative controls.
The Reactor Administrator is responsible for the safe storage and use of the special nuclear material.
The Reactor Safety Committee (RSC) has reviewed and approved all plans and procedures for the usage of the materials in the SCA.
The RSC will review and approve all new experimental plans and procedures prior to implementation. The RSC was formed at the request of the NRC in 1968 to review and approve experimental procedures performed with our AGN-201 reactor.
There must be a minimum of two persons in Room 23 whenever operations involving special nuclear material in the assembly are in progress.
Access to Room 2.1 and the fuel storage containers will be controlled by the restricted distribution of keys.
This distribution will be as follows:
The Dean of the College of Engineering, the Reactor Administrator, and the Reactor Supervisor will each hold one key to Room 23 (the suberitical facility room).
Other personnel, authorized by the Reactor Administrator, may have access to a key to Room 23 kept in a secure, combination-locked box.
The Dean and the Reactor Administrator will each hold one key to the locks securing the fuel storage container and the assembly BCCOss-Cover.
The Reactor Administrator will consider all requests for che transfer and use of materials covered under this license at the Accelerator Center.
Transfer of material to the
. Accelerator Center will not occur until approval has been granted by the Reactor Administrator.
Records will be maintained of the date and time of transfers, and of the responsible user to whom the materials were transferred.
70.24 Additional requirements.
(a)
Criticality alarm.
The criticality alarm is a Ludlum Model 300 remote area monitor, or equivalent.
It is installed six feet away from the assembly tank and has a Type 18503 detector hard mounted to the monitor case.
The inutrument specifications are provided as enclosure (5).
(b)
Emergency evacuation procedure.
The procedures given below will be carried out under the direction of-the person responsible for the assembly at the-time the emergency occurs, All power to the pump and solenoid drain valve will be' shut off by placing the drain valve and pump. power switch in1the~
~'
9 tsU college of Engineering 9/30/97
OFF position.
(This step backs up the function performed wl.ei; the criticality alarm is activated.)
The portable gamma survey meter will be taken from Room 23 by l
l the evacuating personnel.
Once all personnel are out of Room 23, the door will be I
closed and a radiation survey will be performed in all areas adjecent to Room 23.
If radiation levels exceed 10 mrem /hr outside of Room 23, the building fire alarm will be activated to evacuate the entire building.
Pull stations for activating the fire alarm are located in the main corridors near the stairs as shown in the basement building floor plan provided as enclosure (6).
Exits and access routes
- .o and from the basement are shown on the building floor plans provided in as enclosures (6) and (?).
Building ventilation will be secured by pushing the " Penthouse Power Emergency Trip" switch located on the wall facing the Reactor Supervisor's office (Room 15).
The Reactor Administrator, the College of Engineering Dean, the Radiation Safety Officer, and the Reactor Supervisor or their designated alternates are all on an emergency call list and will be notified of the emergency.
Building reentry will be directed by the Reactor Administrator in consultation with the Radiation Safety officer (or their alternates).
Emergency equipment and communication and alarm systems will be tested annually.
Emergency procedures will be distributed to permanent staff and personnel who will work with the SCA.
Periodic review of these procedures will be accomplished by drills.
10 ISU College of Engineering 9/30/97 ~
1
ENCLOSURE (1)
U. S. NRC Materials License No. Il-23780-01 l
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AmendmenUNo. 2 I
ts sH u.a. NV%s AM C;s!Ut.AT02Y COnA6MS$loN MATERIAL 0 LICENSE l
l irsuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganlution Act of 1974 (Public 1.sw 93-438), and Title 10, i
Code of Federal Regulations Chapter I, Parts 30,31,32,33,34,35,40 and 70, and in reliance on statements and repesentations i
beretofore made by the licensee,a licenso is hereby issusJ authorizing the licenue to recelve, acquire, poness, and transfer byptoduct, l
Sourte, and special nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated below; to l
l deliver or transfer such material to persons authortred to receive it in accordance with the regulations of the applicable Part(s). Thl:
1 li:enu shall be deemed to crataln the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and la I
subject to all applicable rules, regulations and orders of the Nuclear itegulatory Commission now or hereafter in effect and to any l
condition specified below.
i ucenue In accordance with letter dated I
- 3. beense num "9, 1994, l
l December I-t Idaho State University 11-27360-01 is amended in d
its entirety to read as followst E
M
(
2 Technical Safety Office 4
Box 8106
- 4. Expiration date July 31, 1999 4,
Pocatello, Idaho 83209 5
[
he,','n$ so, 030-32322/lDA-33-1
[
4 6 By produtt, source, and/or
- 7. Chemical and/or physical
- 8. Mulmum amount that licensee H
4 special nwlear material form may possen at any one time l'
f under this license
,4 W
A, Any byproduct material A. Any, excep6 sealed A.
Not to exceed q
with Atomic Numbers 3 sources 250 millicuries per k
through 83, inclusive, radionuclide, with I',
I' except as specified a total possession
(
below limit of 5 curies h
{pf j
B.
H.drogen-3 B. Any, except scaled B.
10 curies L4 sources h,
C.
f Ary byproduct material C.
Any, except sealed C.
Not to exceed t
with Atomic Numbers sources 1 millicurie per g
'4 Bbl 03, inclusive radionuclide, with li
- !4 a total possession 1;
h limit of b
j 100 millicuries h
1 D.
Any byproduct material D.
Scaled sources D.
Not to exceed 1 d
]
with Atomic Numbers 3-(Registered pursuant curie per source, h
!p'4 l4 103, inclusive, except to 10 CFR 32.210 or total possession
!4 as specified below equivalent Agreement limit 10 curies h
State regulations) l(
4 p
h E.
Plutonium-239 E.
Sealed sources L
100 grams t1 (Regi;tered pursuant T
14 to 10 CfR 32.210 or i
li equivalent Agreement I
h State regulations)
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14 i
C+sium-137 I.
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SUPPLEMENTARY SHEET 030-32322/IDA-33-1 l
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. d-Amendment No.
2-l l
1 I
N I
G.
Uranium-233 G. Sealed sources G.
0.5 grams I
(Registeredpursuant E
to 10 CFR 32.210 or E
i equivalent Agreement I
N Stateregulations) l s
H..
Thorium-229 H. Sealed sources H.
0.5 grams N
M (Registeredpursuant u
,c,to 10 CFR732.210,or E
4
",,e' equivalent Agreement N
q State regulations)
W E
l.
Californium-252
- 1. Sealed sources 1.
Not-to exceed y
(Registeredpursuant 50 millicuries per l
to 10 CFR 32.210 or source, total d
N equivalent Agreement possession limit
{
State regulations) 200 millicuries
.J.
Hydrogen-3 J. ' Sealed sources, J.
200 curies W
-Tritium targets W
W (Registered purs'uant E
N to 10 CFR 32'.210 or h
(
equivalent Agreement W
State regulations) n (l
K.
Americium-241 K. Scaled source K.
50 curies j
(Registered pursuant g
g to 10.CFR 32.210 or g-j equivalent Agreement g
j Stateregulations) 4 4
L.
Cesium-137 L. Sealed sources L.
Not to exceed 15 W;
i (Registeredpursuant millicuries per kl 4
to 10 CFR 32.210 or source, total ni l4 equivalent Agreement possession limit of E
4 State regulation and I curie h
incorporated in a compatible gauging E
4 device as specified W
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Americium-241 M, Sealed sources M.
Not to exceed 300 y
y (Registeredpursuant millicuries per y
yi to 10 CFR 32.210 or source, total y
equivalent Agreement possession 5 curies W 4
State regulation and y
f incorporated in a p
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4 4
device,as specified W
in item 9 of this y
y license) y h l N.
Carbon-14 N. Labeled organic N.
Not to exceed 200 E
l material mierocuries W
g Ls H
s 3.
Authorized use:
E s
E pM A-through M.
Research and development as defined in 10 CFR 30.4, academic and N
technological instruction, calibration of licensee's instruments, and
-s; animal studies.
W "i
,i!
L. and M.
To te used in portabic gauging devices which have been registered E
f,_
pursuant to 10 CfR 32.210 and distributed in accordance with an Np" E
- i; or Agreement State specific license to persons specifically licens,.d k
i by the NRC to receive, possess and use the devices.
E
- a u
i N.
Release of carbon-14 labeled organic mtterial into two of the streams E
"i' identified in License Condition 10.C.
Each release will be limited E
to 25 microcuries of carbon-14. No more than 100 microcuries of F!
3 cerbon-14 may be introduced into a particular stream in a twelve-El d3l month interval.
Ei E!
A E
'i E
]3' CONDITIONS y
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9 10.
A.
Licensed material identified in items 8. A. through 8.M. shall be used only at i
j the licensco's facilitics located at :
E 4
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- i' 1)
Idaho State University, 741 South 7th Street, Pocatello, Idaho.
E F#
2)
University Place, 1776 Science Center Drive, Idaho falls, Idaho.
E I4 Fl fi 3.
Licensed material identified in items 8.L. and 8.M. sha's1 be used at temporary F!
I job sites of the licensee anywhere in the United States where the U.i Nuclear F
6 Regulatory Commission maintains jurisdiction for regulating the use of licensed G
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MATERIALS LICENSE Idda w Meeum Numte N
g SUPPLEMENTARY 8HEET 030-32322/IDA-33-1 g
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Amendment No.
2 g
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- 10. (C 6 Lif.ued) p i
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C.
1.
Umsad intwial identified in item 9N. above may be introduced in the y
4 M ootni!Acn3 Deep, or Toponce Crceks, which traverse the Cache and Caribou y y
National Forests and the Curlew National reasslands.
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W 2.
l.icensed materini shall be used only under the following conditions:
y I
W a.
Specific approval is given by the Idaho State University Radiation y
y Safety Committee.
y g
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The licensee obtains written permission to use radioactive material y
- y at the proposed site from the appropriate authorities (er persons) g g
who r.iintain administrative control over the property, p
2 h
q 11.
1he Radiation Safety Officer for this license is Thomas F. Gesell, Ph.D.
p
)
12.
Licensed material shall only be used by,- or under the supervision of, individuals f
designated by the Radiation Safety Committee, Scott S. Ilughes, Ph.D., Chairperson, g
[4 13.
A.
Sealed sources and detector cells shall be testca for leakage and/or contamination at intervals not to exceed 6 months or at such other intervals as
,j specified by the certificate of registration referred to in 10 CFR 32.210.
B.
Notwithstanding Paragraph A of this Condition, scaled sources designed to emit f f
. alpha particles shall be tested for leakage and/or contamination at intervals j,l g
q not to exceed 3 months.
j;l Y
C.
In the absence of a certificate from a transferor indicating that a leak test E
has been made within 6 months prior to the transfer, a scaled source or E
5 detector roll received from another person shall not be put into use until
(
f tested.
D.
Scalec' sources need not be leak tested if:
M h
.(i) they contain=only hydrogen-3; or d
(ii) they contain only a radioactive gas; or h
M h
(iii) the half-life of the isotope is 30 days or less; or N -
(iv) they contain not more than 100 microcuries of beta and/or gamma emitting h
material or not more than 10 microcuries of alpha emitting material; or y
y (v) they are not designed to emit alpha particles, are in storage, and are not 5
'h being used, liowever, when they are removed from storage for use or p
5 4
5 hi
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13.(Continued)
N y
W transferred to another person, and have not been tested within the W
4 required leak test interval, they shall be tested before use or transfer.
H i s No sealed source or detector call shall be stored for a period of more W
4 than 10 years without being tested for leakage and/or contamination.
H l
A l
i E.
The leak test shall be casable of detecting the presence of 0.005 microcurie of M
( 4 radioactive material on tie test sample, if the test reveals the presence of W
s 0.005 microcurie or more of removable contamination, a report shall be filed N
s with the U.S. Nuc1 car Regulatory Commission in accordance with 10 CFR 30(b)(2),
h 4
and the source shall be removed immediately from service and decontaminated, h
l s
repaired, or disposed of in accordance with Commission regulations. The report E
shall be filed within 5 days of the date the leak test result is known with the E
U.S. Nuclear Regulatory Commission, Region IV, 611 Ryan Plaza Drive, Suite 400, h
g Arlington, Texas 76011, ATTlh Director, Division of Radiation Safety and F
g Safeguards. The report shall specify the source involved, the test results, E.
- r and corrective action taken.
W W
4 f.
Tests for leaktige and/or contamination shall be performed by the licensee or by p
.j other persons specifically licensed by the Commission or an Agreement State to y
W Perform such services.
El 4
.1 F1 i
14.
Maintenance, repair, cleaning, replacement, and disposal of foils contained in p
2]
detector cells shall be performed only by the device manufacturer or other persons W
specifically authorized by the Commission or an Agreement State to perform such E!
4 services.
Q 4
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15.
A.
Detector cells containing a t!tanium tritide foil or a scandium tritido foil i
j shall only be used in conjunction with a properly operating temperature control s q
mechanism which prevents the foil temperature from exceeding that specified by
(
4 the manufacturer and approved by U.S. Nuclear Regulatory Commission.
4 w
2 8.
When in use, detector cells containing a titanium tritide foil or a scandir.n s
j tritide foil shall be vented to the outside, g
E 16.
Each portable nuclear gauge shall nave a lock or outer locked container designed to y
g prevent unauthorind or accidental removal of the sealed source from its shielded g
2 position.
The gauge or its container must be locked when in transport, storage, or p
j when not under the direct surveillance of an authorized user.
p I
F(W G
17.
Any cleaning, maintenance, or repair of the gauge (s) that requires removal of the P
source rod shall be performed only by the manufacturer or by other persons specifically licensed by the Commission or an Agreement State to perform such y
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=============_wm=====;
. NRO FORM 374A U.S.NuottAR RioVLATORY COMMIS$40N PAGE OF at PAGES l m
p' Lku Huna.rr g
11-27380-01 N
MATERIALS LICENSE Ma or Refretace Hon.ter N
- SUPPLEMENTARY SHEET 030-32372/inA 11 1 N
N I
g Amendmont Nn 9
N N
I I
p l
N l
- 18. The licensee is authorized to hold radioactive material with a physical half-life of N
4 less than 120 days for decay-in-storage before disposal in ordinary trash provided:
N l
A E
q A.
Radioactive waste to be disposed of in this manner shall be held for decay a W
l 4
minimum of 10 half-lives.
E 4
N i
B.
Before disposal as ordinary trash, byproduct material shall be surveyed at the h
i i
y container surface with the appropriate meter set on its most sensitive scale W
g and with no interposed shielding to determine that its radioactivity cannot be W
4 distinguished from background. All radiation labels shall be removed or W
q obliterated.
H i
H
.)
C.
A record of each disposal permitted under this License Condition shall be N
y retained for three years.
The record must include the date of disposal, the h
4 date on which the byproduct material was placed in storage, the radionuclides W
j disposed, the survey instrument used, the background dose rate, the dose rate W
w measured at the surface of each waste container, and the name of the individual N
2 who performed the disposal.
W 19.
The licensee is authorized to transport licensed material only in accordance with n
the provisions of 10 CrR Part 71, " Packaging and Transportation of Radioactive h
i Material."
W 4
9 20.
Licensed material shall not be used in or on human beings.
W a
h j
21.
The licensee shall not use licensed material in field applications where activity is F
j released except as described in the letter dated December 9,1994.
k H
E j
22.
Scaled sources or detector cells containing licensed material shall not be opened or E
j sources removed from source holders by the licensee.
W
.i k
q 23.
The licensee shall conduct a physical inventory every 6 months to account for all p
g sources and/or devices received and possessed under the license.
W 4
h 24.
Exrerimental animals or the products from experimental animals, that have been s
y administered licensed materials shall not be used for human consumption.
y
)
25.
In addition to the possession limits in item 8, the licensee shall further restrict f
g the possession of unsealed licensed material to quantities less than 10' times the g
y applicable limits in Appendix C of 10 CFR Part 20, as specified in 10 CFR 30.35(d),
p g
40.36(b), and 70.25(d).
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l' NRC FORM 374A u.S. NUCLEAR PEQULATORY COMMISSION PAGE y
or 9
PAGE9 g
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11-m 80-01 N
MATERIALS LICENSB twcLa w w e m Nvmte g
h SUPPLEMENTARY SHEET 010-3217 ? / T hA-3h1 N
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26.
Except as specifically provided otherwise in this license, the licensee shall W
s' conduct its program in accordance with the statements, representations, and W
A procedures contained in the documents, including any enclosures, listed below. The h
y U.S. Nuclear Regulatory Connission's regulations shall govern unless the statements, E
N representations, and procedures in the licensee's application and correspondence are W
q more restrictive than the regulations...
E W
s r
g A.
Application dated September 20, 1994 E
i B.
Two letters dated December 6,1994 W
s C.
Letter dated December 9, 1994 W
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FOR THE U.S. NUCLEAR REGULATORY COMMISSION E
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~ <4 C/. N,ftetqc.
[
j Date By Q
aterials Branch y
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Region IV;WCf0 g!
Walnut Creek, California 94596
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ENCLOSURE (3)
Water Handling System Diagram l
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ENCLOSURE (4) j Water Handling System Electrical Diagram t
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1 ENCLOSURE (5)
Criticality Monitor Specifications 1
e 45 Encle:ure 5 udlum MODEL 300 l AREA MONITOR The Model 300/ Area Monitor utilizes an automatically reset binary train to dore the count rate infor-mation, providing the capability of high alarm speed with good statistleal stability A chotee of one of three different GM detectors casi give a ranee of up to 200 R/Hr. Foolproof operat10n is insured by f ailure. A green light monbeable D size batteries allowing continuous operation even during pow the use of stand by rechar 4
or, driven by normal back ground gamma or a small source, proves the unit to be in counting operation. The green light will go off only if the unit has failed, radiation below set point, or if the Red alarm is on. The unit is also provided with a continuous operating, three de-cade log meter, g
$PECIFICATIONS CONTROLS Alarm Rangei Siondord unit supplied with on tHD 712 CONTROL 5 THAT ARE ACCE551BLE FROM fpONT OF 4
with alarm eonge from 0 03 to 300 MR/Hr.
INSTRUMENT BY REMOVINo COVER PLATE For on olarm range of 0.5 to 2000 MR/Hr. spect-Time Bones A four position top switch and trimmer fy ond LND 714 GM Tube.
for on alarm range of 2 MR/Hr to 200 R/Hr.
Potentiometer to select reset time base, specify and (ND 716 GM Tube.
Pulsen tight position top switch to select number of R e solution 100 re croseconds with the 712s 20 micro-Puises to olorm, seconds with the 714 and 716.
Power Three position switch to select "of f" "on" Pulse Rote: GM 712 - 23 pulses /second/MR/Hr.
ond "chorge". Chorse position is to be used for GM' 714 - 2 pulses /second/MR/ Hr, fast chorging of botteries. Trickle charge is pro-GM 716 - 0.3 pulses /second/MR/ Hr.
vided in "on" position.
Monitor A potentiometer to set trigger poln for the Roset Time Bose Adjustable from 0.6 milliseconds to green light monitor.
6 seconds.
Calibrotions A potentiometer to calibrate log meter.
Number Of Pulses to Alarm. 5et at 5,10, 20, 50,100, 200. 500, or 900.
CONTROLS NOT UNDER COVER PLATE Detector Voliage Adivsioble from 200 to 1200 volts.
Reset Push Lution to reset cloem and meter.
Normal c,perollon at 500 volts.
Discriminotion 40 Millivolts.
CON 1 Roll ACCES$1BLI BY RIMOVING Ch.,55t$
local Atorm indicolor. A Sonalert audio and a flosh.
FROM CABINIT ing red light.
H, y,i potentiometer to odlust High Voltage from 200 Poweri 115 v - 60 CP5 line power. Pilot light Indicates to 12f'O volts, line power operation.
Stord Byi Four each internal rechargeable N'Cd "D" EXTERNAL CONNECTIONS selle for more thon.100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> operation without line power - in o non-clorm state.
Eternal connections are provided for remote clarm ond remove olarm deoctivotion, Detector Connector Series "C" quick disconnect.
Meteri A 4 inch log meter covering three decodea with PRICE Model 300/ Area Monitor 0 02 to 20 MR/Hr preseniotion standord.
$se, 10" wide by 8" toll by 8" deep.
Complete with stand-by botte rie s, one detector, and weighti 12 pounds with botteries.
power cord.
Mounting s Bench top or shelf.
$575.00 F06 Sweetwater Temos Hnish. Brown epony point on steel cabinet, clear on-Spore detector assemblies $75.00 each. Specify detector odised panel Silk screened nomsnclosure, number with order.
LUDLUM MODEL 300S/ NEUTRON SCINTILLATION AREA MONITOR Specifications are essentiaUy the same as ".he standard Model 300/ Area Monitor with the exception that the Meter Dial wlU read out per customer's specification.
PRICE Model 3005/ Neutron Scintillotton Area Monitor base price $500.00. Select
- Detector, Model 421 Thermal Scintillouon Ne u tr on Doctor..............e o. 5250.00 Model 42 2 Fast Neutron Scintillation Detector.
...............oo.
5250.00 Model 42 4 Neutron Detector with 10" sphere of polyethylene.... eo. $525.00 s
Specifications for the Neutron Scintillators wlU be found in the Ludlum general catalogue.
LUDLUM MODEL 300P/ PROPORTIONAL NEUTRON AREA MONITOR Specifications are essenusuy the same as the standard Model 300/ Area Monitor with the fol.0 wing exceptions:
High Voltage Adjustable from 400 to 2400 volts.
Discriminationi Adjustable from 2 to 60 niillivolts.
Meter Presentationi To read out in cu. mer preference.
PRICE Model 300P/ Proportional Neutron Areo Monitor base unit price - $650.00.
Detectori A one Inch thick poroffin r ioieroted BF 3 Detector os described with the Model 15 in the genero! catologue - so. $300.00.
Other types of proportional neutron detectors ovalloble upon request.
SWEETWATER, TEXAS 79556 LUDLUM MEASUREMENTS, INC.
g 50lOak Street P. O. Box N8 (915) 235 5494
ENCLOSURE (6)
Basement Floor Building Plan i
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ENCLOSURE (7) i Ground Floor Building Plan 1
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ENCLOSURE (8)
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i ENCLOSURE (9)
Pocatello Area Map
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Schools Points of Interest
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