ML20137G324
| ML20137G324 | |
| Person / Time | |
|---|---|
| Site: | 07001721 |
| Issue date: | 02/14/1978 |
| From: | Maki C CLEVELAND-CLIFFS IRON CO. |
| To: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| Shared Package | |
| ML20136B820 | List: |
| References | |
| 08918, 8918, NUDOCS 8601170672 | |
| Download: ML20137G324 (14) | |
Text
c-y:
otegu,a:ory Joc?ie: :i'e' 7s-/7a/
ii[CElVEU 373 R.B 22 P: 7 Y
g/ h C. A. DAWE. GENERAL MANAGEn.
tic E GY COMM.
H. W. REMEOLD. Ass'T MANA5 504 SPRUCE STREET G
ISHPEMING, MICHIGAN 49849
- o. C. FORSBERG, Ass *T MANAGER.
)N C. H. BOYUM. Ass'T MANAGER, ADMINhdeAdfs-Re n
PEONE 906-486 9941 February 14, 1978
_30CIVED BYp Date..
Director of Nuclear Material Safety and Safeguards
,'g,
- 0 U. S. Nuclear Regulatory Commission By. [. mj,g, Wtshington, D.C. 20555 From.
Gentlemen:
Cy to.
Action Compi,,,,, /,j,7,2'
/,
The enclosed information, submitted in triplicate, is a requ m m
amend our Special Nuclear Material License No. SNM-1492, issued Sept. 19, 1974, to add one additional Texas Nuclear Neutron On-Line Activation Analysis system (Nola) identical to the one already authorized under this license. With the exception of Cleveland-Cliffs Iron Company's principal officers, all statements, representations and/or conditions of use submitted with our initial application dated June 14, 1974, and supplemental application dated July 22, 1974, are still valid and applica-ble to this request.
The principal officers of The Cleveland-Cliffs Iron Company are as follows:
President S. K. Scovil Senior Vice President - Operations E. B. Johnson General Manager - Mines G. A. Dawe All are U. S. citizens It is our hope that you can expedite the issuance of the amendment.
If you do require additional supporting information, please let me know at your earliest convenience.
Very truly yours, l,,
D THE CLEVELAND-CLIFFS IRON COMPANY L
By h/ /
2 Ud 91978 > !
' Carlo w. Maki, 9
D
-fg Instrumentation Engineer y
gh Operations Research 0%%
'N Encs.
r 8601170672 851114 REG 3 LIC70 SNM-1492 PDR
e
.pa p
m i
Technical Data
~
..T is system will be used for elemental determinations
<~
in iron ore and is being supplied to Tilden Mine by Texas Nuclear, 9101 Highway 183, Aust.in, Texas 78758.
l
~
The system is shown on a ilrawing labeled " Schematic Re-presentation of NOLA,I".. The slurry is c'ycled con-tinuously through the irradiate cell and the detector for analysis.
The, general layout of the NOLA System is shown on the drawing labeled "Nola I Silica Analyzer".
The system
'~
will.be installed in'
~774.a&J /4,ar - fooc(NerA ro(
' * * }M op g e a.,
t
'4 8 A -/ O 2_
/
as shown on, drawings' This room has solid floors and walls and can easily be secured against unauthorized entry.
The environmental conditions at the installation site are TeaprerAmar A.JD ' HG ar'6, rri
- t o;> vn.no.i g n
~ - - - -
- -.... e...
.g g..
g.
g e
4 g
g O
O
~
m
~
g.
A A
SLURRY HANDLING SYSTEM r----------------------
n-
$fNPUT l
IRRADIATOR
~-
PUMP pr p
REClRCULATE CI
"~
' = -
TIME o
SEQUENCE j
\\
O_ _-:--
o TWO-WAY o,~
CONTROL
?
VALVE l
I I
' ~ ~ ~
- . y O--
- N.
y !-
p o
DENSITY 4
1 CHARGE-FLUSH NEUTRON
-y ELEC-p U
DENSITY GAUGE h
m I" ~
~7 DETECTOR s
t i
I ELEC g
I l
'O~-
-J
' ' -L
~'
O' '-
O O' '-
O
'T-RAY x
o- ~~__ o DATA SOURCE
,T
~~_ o
(
)
m
- 1. -
-m.
COMPUTER + 1NTERFACE 1
L
- -.~ - --
_^ ^ ^ ' '
\\
/
\\
\\
PRINTER *-
U XN N
r r-CONTROL AND A
\\\\\\NN\\
x DATA ACOUISITION pETECTOR SCHEMATIC REPRESENTATION OF NOLA I
~
' o.
. o o_:
o o
a f
/
DENSITY OAUGE
}
N
]#
A rs.
I J
...(.
if'uIc,
.g5 j.h p
g.t ik
- "'N i f.
=="a
/
N /s g
'l t
\\
j 64 dp;ji l
r
,.3 -
(,
m j\\\\
I b
Swnar
' (,4 ',', * * '
u 14ANDUNG lg SYSTEM
/
N g- '
g' w
f i
COUNTEf; CONTn01. AND DATA I
f a
ACQUISITION UNIT t
NOLA I SILICA ANALYZER
- ~m.
.I f
'g 9
8 L
.o-o.
The principal hazards of concern in this system are:
. a)
Exposure to radiation outside the shield under normal operating c,onditions; b)
Failure of the source capsule inside the shiel'd; c)
Exposure to radiation under emergency conditions;
. d)
Disposal of the activated materials.
Density Channel
~
The density channel is shown in the drawing-titled "Nola I e
Density Gauge".
The 5176 source head acts as a complete storage container for the 500 mci Cs-137 sealed source, Texas Nuclear i
y Model 570-57157C, both prior and subsequent to installation of.
I the system.
The radiation levels one foot from any accessible
~
surf' ace are le'ss than 0.5 mR/hr.'
In the event work must be done inside the detector box, the shutter will be closed and locked before such work begins.
This source will be leak tested 3
at 3. east once every three years, in accordance with Texas Nuclear procedure QT/lK (see appendix).
No waste disposal is involved.
S p
If the use of the gauge is discontinued, the source will be returned to Texas Nur: lear for disposal.
~
'8111' con Channel The construction of the shield is detailed on the drdwing titled
..' Neutron Source Shield" (see appendix) and schematically shown in the figure titled "Nola I'Irradiator".
The source is threaded onto a stud at the bottom of the itiner cell.
The irradiate cell slips over the source and can be installed and removed without moving or unshielding the source.
This construction is'shown on the drawing labeled " Inner source sh'.ald Assembly".
(see appendix)
C.
4 G
u a
~
.O-
~
' o.
n.
SLURRY LOOP TUBIN G NAI(TI)_y RAY DE_TECTOR x
x G
i x
9 p,)
f e
N ;L e 7 _,.y 93 fr-T..
y
/
/
} $ b -
j
/
~.
j e
r.
TUNGSTEN O
~
NUCLEAR CHICAGO COLLIMATOR MODEL 5176 LEAD l
DENSITY GAUGE HEAD COLkiMATOR NOLA I DENSITY GAUGE 4
~.
.C p~..-
/
.O.
~.
h.l!Nh{\\
~
LEAD SHIEL6 WATERS NL E
j! -
~'
s
- N l
.ir T
l
.~0.\\ ?-
/
.k N, y'
/
I s
< r,. c #..-
/
_ =. ~. s
'y s
. /,
7 s.
NEUTRON
-~
SOURCE N.l'l_
~
~
ENCAPSULATED ACTIVATION
~
i CELL l
SOURCE TANK 1
~ ~ _.
l.
NOLA I
IRRADIATOR y-
..O, O
1 1
The Plutonium 238-Beryllium neutron source contains approximately 2.9 grams of Plutonium-238 as an oxide mixed with 15.2 grams of Beryllium.
The' neutron 8
emission rate of the source is 1.1 x 10 n/sec., and the source was fabricated to the specifications shown on the drawing labeled "PuBBe-Source Capsule" by Monsanto Research Corporation, Dayton, Ohio.
An analysis of pressure build-up due to alpha particle decay of the contained Pu-238 was made.
This analysis was based upon a maximum loading of 4.24 grams of PuO '
2 80% enriched in Pu-238 at an initial' pressure %f 'one atmosphere.
We assumed that the Helium obeyed the Ideal Gas Law and that ambient temperature was 70 C.
We additionally said that 30% of the internal volume was void due to the approximate 70% compaction of theor6tical density that one gets after pressing the PuO -Be pellet.
2 In the~a6'tivation analysis system one can estimate the 4
useful life of the source to be.80 years, based on the' required sensitivity of the measurement.
This would mean a pressure build-up of approximately 400 psia.
One can calculate the bursting pressure of the inner capsule, I using the tensile strength,of 304 SS as.85,000 psi,,to be ;,.
greate'r than 6,400 psia.
Prototypes of this capsule
' ave been tested under American National Standards h
Institute procedures and classified E 55535.
e e
.h.
l L
O o
Radiation exposure rates outside the neutron source shield are C1 shown at typical survey points on the drawing labeled " Neutron Source Shield".
The source,itself is shielded'as shown, with l
lead and water on all sides except the top, which is covered by 33 inches of* oil.
This filling insures access to install orfk remove.the teflon irradiation cell without undue radiatio'n exposure (reference Cell Check and Removal Procedure).
.The cover plate has a cable and lock to insure that only authorized personnel have access to the cell.
As usual,*the shield is
. massive and the exposure rates are very low due mainly to the high sensitivity of the system detectors rather than personnel exposure considerations.
TPa sensitivity of these detectors also pro,vides an additional margin of safety, since they will indicate a change in performance if some abnormality occurs.
~
Clearly, exposure.to radiation outsida the shield is mininal.
The large water shield also has a low water warning system,
({}
consisting of a Cutler-Hammer Level Probe, Model 13653H6, located approximately one-half inch below the tank top, and connected to a Cutler-Hammer standard duty fail safe transistor sensi.tive relay, Model 13535H110-1.
The alarm circuit will indicate when the water level is approximately one inch below I
the tank top.
At that time, one would not observe any appreciable f
increase in the dose rates as presented.
Lights on the control L
panel indicate the status of the water level.
A contact closure
[
is also provided for remote alarms' if desirable.
l
?
'The water shield has a chemical additive to inhibit corrosion and organic growth identified as NALCO 39,L, and supplied by Nalco Chemical company
'l.
.,.i,f : <*' y q#-
~5757 Bellaire Blvd.'
- T
,t
,* Houston, Texas.
l Water replenishment, if ever necessary, would' be a manual operation as there is no provisions for automatic filling.
. (:?
~
- e 4
o o
(-
The physical location of the sample room the building con-struction and gen'eral house-keeping conditions make it unlikely that conditions could exist which would endanger the shielding
~
properties of the primary container.
Although we cannot envision the* accident, if such occurred, we would attempt to evacuate personnel from the area of the source, notify the U. S.-Steel Radiation Safety Office and Texas Nuclear Health Physics and await instructions and/or the arrival of trained personnel to evaluate the situation.
However, the dose rates are not so high as to preclude maintenance on the tank.
One can estimate the unatt' nuated dose rate at a meter to be slightly more than e
100 mrem /hr by using:
8 a) neutron emission = 10 n/sec, b) average first collision dose in tissue =
~
-9 2
4.0 x 10 rad /n/cm,
~
c) mean quality factor = 8.5 for Pu8-Be neutrons,,
()-
'.d) adding the gamma contribution from both the 4.43 MeV state of C-12 and the 2.2 MeV
?*
emission from neutron capture in Hydrogen.
Additionally note that the source is not unshielded if all tlic water is out of the tank.
There is a 5 inch oil bath plus the irradiation cell and the 20 inch O.D. lead half-annulus to consider.
In fact, except for near the floor level, and the tank end away from the large crystal detector, the total dose
~ rates would not exceed 15 mrem /hr at the-neares't point of the
(,
shield tank with no water.
Failure of the source inside the shield is remote at best.
This type of capsule construction has been used for some time with few failures, Also, a failure of the source would e
C-8 o
J
~
b' O
change the optimized irradiction geometry and this would immediately affect the operation of the system.
Therefore,
'we propose to leak test this source using the procedure
- entitled " Leak Test of Activation Analysis Sources", (see Appendix) at least once every six months under normal condi-tions, and at any other times the operational data lead us to suspect that some s6brce or cell abnormality.has occurred.
In
'the event the leak test is positive, we will discontinue use
'of the system, secure the room and await further instructions from Texas Nuclear and/or the Tilden Mine Safety Officer.
We believe that even a ruptured source could be safety contained
~
~
for some time in the shield with little probability that con-
~
i tamination would be a hazard outside the container.
The following are, additional items that are an integral part of our program:
lO
'a)
The system will be installed by trained personnel of rexas Nuc1 ear.
b)
Personnel will receive training in the
' operation and hazards of the activation analysis system 2
t by Texas Nuclear personnel.
c). Radiation surveys will be made at the time of installation by Texas Nuclear and copies will be retained for' inspection.
d)
- Personnel working around the activation analysis system will not use personnel monitors.
It is
(
unlikely that any individual can approach a whole body l
dose of 0.125 rem per quarter.
l e)
P ersonnel will not remove' the source from i
the primary shield.
In the event that circumstances lead us to believe that the shield is no longer an integral unit, personnel will.be removed from the area and. Texas Nuclear will be notified.
'~
t C-e g
-Q '
-Q
(*'
f)
The pumping system will not be turned off with material in the irradiate cell during normal operation.
Prior to shutdcwn, we will flush the system with water.
To insure that no material remains in the irradiate ce'll, we will continue to flush hnd drain until the gamma spectrometer count rate approaches background.
g)
In the even. the use of the system is discontinued, the removal and disposal of the radioactive material will be handled by Texas Nuclear.
These points and included procedures will be incorporated in d
the operations manual provided by Texas Nuclear.
There is only very low-level radioactive waste generated in this system.
In operation (reference " Schematic Representation C')
of Nola I") a small sample of iron ore slurry is recirculated through the activate cell and count cell for five nu{.nutes.
It can them be dumped. either into a wast'e line or back into the product line.
None of the activated material is ever released to any area that directly connects to any life support chain.
The iron ore slurry has as its principal constituents Fe O 23 (60-70%) and 'iO
( 3-20%).
Table I lists some data on the more 2
prominent activation reactions pos'sible, consider that in
' operation we put in 100 grams of iron ore for a five minute irradiation every cycle.
For neutron irradiations of this type, the formula i..
Nn'foS where A = Activity 'in curies A"
(3.7 x 101U)
"f= N utron flux S = Saturation factor - (1-e-At)
N = Number of target atoms available O = Activation cross section e
g S
e e
O
~
O-
~
n Element Isotope Activated Type of Reaction - Activation Pt'oduct Half-Life Gamma-Ray Energi and Abundance and Cross Section Threshold Nuclide of (MeV) and.
at 14 MeV (mb)
(MeV)
Activity Relative Abundar 16 (99.8%) *
(n,p),40 16
~
.0 N
7 14~ s e~c 6.1, 7 1-- -
o 0
10
/
$1 28 (92.2%)
(n,p),160 38 A1 2 3 min
.1 77 2
S1
- G Si si30 (3 09%)
(n,y), 110
- s131 2.62 hrs 1.26 ( 0.1) 54 (5.82%)
(n,y), 2500
- 55 Fe Fe 2 7 yrs 0.006 Fe 54 (n,p),375 2.0 Mn aso days cr X-rays
- 56 (91,77) ~
~
56 (n,p),110
'39 Mn 2 58 hrs 0.845 (100)
Fe -
Fe 1.81(30g 2.13 (20F
~
t i
~
g Thermal cross' section e
4 TABLE I k
g d
1
. o O
will. estimate the amount of activity produced per irradiation within an order of magnitude.
However, experimentally it has been determined, in a five 28 minute count. period, that the Si28 (n,p) Al reaction pro-duces about 1.5 x 10-2 Ci of A1 in the system.
28 e
All the other reactions, except Fe54(n,y)Fe55 have comparable cross-sections, but will not produce as much radioactive material as the above reaction because their. half-lives are long compared to the irradiation time.
Therefore, the satu-ration factor for these reaction.s is much smaller.
~
In summary, we propose that no significant hazard exists either to employees or the general public, in the routine release of the amounts of radioactive material produced in this system.
We, therefore, will not make routine monito, ring or sampling par.t of 0
-eur ereer vroere -
i O
C t
4 D
e g
O e
O e
8
,e O
\\
j
1 V
11h v ' _
f-<,,3 _ -
.P
'N July 22,19M July 29, 1974 5 14 The Cloweland-Cliffe Iran campeay
-re or==
Ishpeming, Michigan'49849 x
ym ORie.s CCs OTH ens Dir Licensing (Buchansn)
C USAEC O
O avl Co Ear RO ACTION RECISSA,,
CLisSIFs POST OFFICE FILE CODES U
Docket 70-1721
.... no, cascniptioN Wuse De Unclassif6ed) nsFanneo to eAva nectivro av DATE
-~
information to supplement Application (BuchananfwRage filh7-30 ans zue copy Distribution
.TCa.u..
PDE M
$"RARKee rk I
1614 U.S. ATOMIC ENERGY COMMisalON Mll CONTROL FORM r a.e e*
I""
g U S GovtRNMEPtf PmNTING OFFICE: 1973 - SO3139
r s ~. (r%
REGIULAT0kY FILE CY
~
~.y.,.
.*,e
-)
//0_1721
~
/
N YrMl'Y
.V LLAR MANAGEn RE ARC AN DEVELOPMENT 504 SPRUCE STREET W. NUMM ELA. Assi. M Ah AGER. MICMfGAN MsNES ISHPEMING. MICHIGAN 49849 C. W. LINDROOS. Asst, MANAGEn. REeEARCN AND DEVELOPMENT PHONE 906 485-9941 July 22, 1974 4) r.e,,,m) y
"[-
O 4.&,% e /
J Director of Licensing C'
U. S. ATOMIC ENERGY COMMISSION s
D' Washington, D. C.
20545 s
n
Dear Sir:
The enclosed information, submitted in triplicate, is a supplement to the Cleveland-Cliffs Iron Co. application for a Special Nuclear Material License for a Texas Nuclear Corp. N0LA I silica analyzer, to be used at the Tilden Mine.
Our license application Docket number is 70-1721.
Very truly yours, THE CLEVELAND-CLIFFS IRON COMPANY fi u, e By' Carlo W. Maki Instrumentation Engineer CWM/nmp cc: CWM - w/a PDF - w/a CUK - w/a ATN W. G. Hendrick, Texas Nuclear Corp. - w/a o
e Tilden File OP-48 (NOLA) - w/a 4
O D E1:D il UJ.;Lc Q
y JUL301974 n}
r-1 3
n:nu7n, Il SECitag f
,, wrun F,
a c) lY. ?TW IC14
\\%
P' 9
~
7.
- i k.*
o O-C Technical Data e
This system will be used for elemental determinations in iron ere and is being supplied to Tilden Mine by Texas Nuclear,_9101 Highway 183, Austin, Texas 78758.-
The system is shown on a d'rawing labeled " Schematic Re-presentation of NO'LA I"..
The slurry is c~ycled con-tinuously through the irradiate cell and the detector for analysis.
The general layout of the NOLA System is shown on the drawing labeled "Nola I Silica Analyzer".
The system will be installed in 77 4 45,) ' M,M Coocera recA1. R
. Jggop,7,g, as shown on drawings
__4 8 A
/O 2.-
/
w This room has solid floors and walls and can easily be secured against unauthorized entry.
The environmental conditions at the installation site are Tsu Me rua r A ap d.o ur'o^, ysi Lo Mst.deiEb. ~
~'
.O
..6
. b g
g g
e
(~
e tiy
A
,r3 SLURRY HANDLING r------ ----- -- -- SYSTE M l'
7 l
~
IRRADIATOR PUMP c
RECIRCULATE SEQUENCE k
C TIME
-y
-~ - ~ ~
~T 9
TWO-WAY CONTROL
[
q~
VALVE
_D
~~~
,i ct_
-o DENSITY 4
4 CHARGE-FLUSH NEUTRON
_--y GAUGE
~~
ELEC' SOURCES P
o f ff fff q
DENSITY GAUGE DETECTOR I----
7
~
ELEC
'g
_ f[ ' ~ ;
g a
o G ~~~~~ D 7-RAY i
x g
O DATA SOURCE
=, - - ~
.U O
1NTERFACE g
~ COMPUTER +
\\
s PRINTER 4--
U
\\\\
CONTROL g
DATA ACQUISITION pETECTOR SCHEMATIC REPRESENTATION. OF NOLA I
7 O
.o 9
f
~
~
s.
g A
TA T DI NU DNANo i
.T
~:;
oI i
%shg:ya<
CA S
aI TU pd NQ oC ie q
~...b.a Wy' 4p js(b RET
%*hcq,,
3 N
y xg Uo R
g dg C
E O
Z YL e
j AN A
7,
$g, w,.t h,
A C
Y
,h il I
IL S
Ja I
, f_m i
A eq,,
L t
O 7
N s
e
)c e
SY
.S
=
t e
f'
,6 im G
.G
(
'.)
The principal hazards of concern in this system are:
a)
Exposure to radiation outside the shield under normal operating c,onditions; b)
Failure of the source capsule inside the shiel'd; c)
Exposure to radiation under emergency conditions; d)
Disposal of the activated materials.
Density Channel The density channel is shown in the drawing titled "Nola I Density Gauge".
The 5176 source head acts as a complete storage container for the 500 mci Cs-137 scaled source, Texas Nuclear
.. munce Model 570-57157C,'both prior and subsequent to installation of.
the system.
The radiation levels one foot from any accessible surface are 1e'ss than 0.5 mR/hr.'
In the event work must be done inside the detector box, the shutter will be closed and 2
3) locked before such work begins.
This source will be leak tested at least once every,three years, in accordance with Texas Nuclear procedure OT/1K (see appendix).
No waste disposal is involved.
If the use of the gauge is discontinued, the source will be returned to Texas Nuclear for disposal.
Silicon Channel The construction of the shield is detailed on the drawing titled
" Neutron Source Shield" (see appendix) and schematically shown in the figure titled "Nola I Irradiator".
The source is threaded onto a stud at the bottom of the inner cell.
The irradiate cell slips over the source and can be installed and removed without moving or unshielding the source.
This construction is'shown on the drawing labeled " Inner Source Shield Assembly".
(See appendix)
C w
g g
SLURRY LOOP TUBIN G NAI(T)) y RAY DETE_CT0_R N
b ec y
W
,,5
/
s- >-(,
- 4..
t
.Q@
V
/
~ >.0 - },/
~~
,j '-
e )
NUCLEAR CHICAGO
~
TUNGSTEN O
COLLIMATOR MODEL 5176 LEAD
^
DENSITY GAUGE HEAD COLLIMATOR NOLA I DENSITY GAUGE e
r C-
/
n
]..
-LEAD SHIELD'
~
WATER s
./
.g s
k s\\
,i.
\\\\
1.l. p y
- N i
r jjl! - g. y f.'
Q 5Jjfj,))Nc'
\\ (
j.; ' -[ '/'
f e
q~
E ~iN M ex i
i i
s.
s NEUTRON
\\
N
-l7 SOURCE r
Q ENCAPSULATED i
g ACTIVATION CELL N
/'..
'/
SOURCE TANK
~
/
N N,/
NOLA I
IRRADIATOR
~
e
.o.
o.
()
The Plutonium 238-Beryllium neutron source contains approximately 2.9 grams of Plutonium-238 as an oxide mixed with 15.2 grams of Beryllium.
The neutron emission rate of the source is 1.1 x 108 n/sec., and the source was fabricated to the specifications shown on the drawing labeled "Pu8Be-Source Capsule" by Monsanto Research Corporation, Dayton, Ohio.
An analysis of pressure build-up due to alpha particle decay of the contained Pu-238 was made.
This analysis was based upon a maximum loading of 4.24 grams of PuO '
2 80% enriched in Pu-238 at an initial' pressure of one atmosphere.
We assumed that the Helium obeyed the Ideal Gas Law and that ambient temperature was 70 C.
We additionally said that 30% of the internal volume was void due to the approximate 70% compaction of theorbtical
(,)
density that one gets after pressing the PuO -Be pellet.
2 In the activation analysis system one can estimate the useful life of the source to be 80 years, based on the' required sensitivity of the measurement.
This would mean a pressure build-up of approximately 400 psia.
One can calculate the bursting pressure of the inner capsule,
/ using the tensile strength,of 304 SS as.85,000 psi, to be greater than 6,400 psia.
Prototypes of this capsule have been tested under American National Standards Institute procedures and classified E 55535.
e
.(
t b
a
' b,,'
b Radiation exposure rates outside the neutron source shield are
~
shown at typical survey points on the drawing labeled " Neutron Source Shie1d".
The source,itself is shielded'as shown, with lead and water on all sides except the top, which is covered by 33 inches of oil.
This filling insures access to install or remove the teflon irradiation cell without undue radiation exposure (reference Cell check and Removal Procedure).
The cover plate has a cable and lock to insure that only authorized personnel have access to the cell.
As usual,'the shield is
, mass ve and the exposure rates are very low due mainly to the i
high seasitivity of the system detectors rather than personnel exposure considerhtions.
The sensitivity of these detectors also provides an additional margin of safety, since they will indicate a change in performance if some abnormality occurs.
Clearly, exposure.to radiation outside the shield is minimal.
43 The large water shield also has a low water warning system.
({}
consisting of a Cutler-Hammer Level Probe, Model 13653H6, located approximately one-half inch below the tank top, and connected to a Cutler-Hammer standard duty fail safe transistor sensitive relay, Model 13535H110-1.
The alarm circuit will indicate when the water level is approximately one inch below the tank top.
At that time, one would not observe any appreciable increase in the dose rates as presented.
Lights on the control panel indicate the status of the water level.
A contact closure is also provided for remote alarms if desirable.
The water shield has a chemical additive to inhibit corrosion an.d organic growth identified as NALCO 39-L, and supplied by Halco Chemical Company
.... /..
5757 Bellaire Blvd.'
d^
' Houston, Texas.
Water repicnishment, if ever necessary, would' be a manual operation as there is no provisions for automatic filling.
e
r 9
9
{'
The physical location of the sample room the building con-struction and general house-keeping conditions make it unlikely that conditions could exist which would endanger the shielding proporties of the primary container.
Although we cannot envision tho' accident, if such occurred, we would attempt to evacuate personnel from the area of the source, notify the U. S.-Steel Radiation Safety Office and Texas Nuclear Health Physics, and await instructions and/or the arrival of trained personnel to evaluate the situation.
However, the dose rates are not so high as to preclude maintenance on the tank.
One can estimate the unattenuated dose rato at a meter to be slightly more than 100 mrom/hr by using:
8 a) noutron omission = 10 n/ soc, b) average first collision dose in tissue =
~9 2
4.0 x 10 rad /n/cm,
c) mean quality factor = 8.5 for Pu8-De neutrons,.
()
.d) adding the gamma contribution from both the i
4.43 McV state of C-12 and the 2.2 MeV,
emission from neutron capture in Hydrogen.
Additionally note that the source is not unshielded if all the water is out of the tank.
There is a 5 inch oil bath plus the irradiation cell and the 20 inch 0.D. Icad half-annulus to consider.
In fact, except for near the floor level, and the tank end away from the large crystal detcetor, the total dose rates would not exceed 15 mrem /hr at the nearcs't point of the shield tank with no water.
Failure of the source inside the shield is remoto at best.
1 This type of capsule construction has been used for some time with few failures.
Also, a failure of the source would C
e
.o o
change the optimized irradiation geometry and this would s
immediately affect the operation of the system.
Therefore, we propose to leak test this sourco using the procedure entitled " Leak Tcst of Activation Analysis Sources", (sco Appendix) at least onco every,six months under normal condi-tions, and at any other times the operational data lead us to suspect that come cobreo or call abnormality has occurred.
In the ovent the leak test is positivo, we will discontinue use of the systom, securo the room and await further instructions from Texas Nuclear and/or the Tilden Mine safety officer.
We beliovo that avon a ruptured source could be safety contained for como timo in the shield with littic probability that con-tamination would be a hazard outside the container.
The following aro, additional items that are an integral part of our program:
a)
The system will bo installed by trained personnel of
()
Texas Nuclear.
b)
Personnel will receive training in tho operation and hazards of the activation analysis system by Texas Nuclear personnel.
c)
Radiation surveys will be made at the time of installation
~
by Texas Muclear and copios will be retained for~ inspection.
d)
. Personnel working around the activation analysis system will not uso porsonnel monitors.
It is unlikely that any individual can approach a whole body dose of 0.125 rom por quarter.
e)
P ersonnel will not remove the sourco from the primary shiold.
In tho event that circumstancos load us to believe that the shield is no longer an integral unit, personnel will be removed from the area and Texas Nuclear will be notified.
C G
6
r f)
Tho pumping system will not be turned off with material in the irradiate cell during normal operation.
Prior to shutdown, we will flush the system with water.
To l
insure that no material remains in the irradiato cc11, we will continue to flush hnd drain until the gamma i
l spectromoter count rato approaches backgr,ound.
D 1
g)
In the event the use of the system is discontinued, the removal and disposal of the radioactive material will be handled by Texas Nuclear.
These points and included procedures will bo incorporated in the operations manual provided by Texas Nuclear.
l There is only very low-level radioactive wasto generated in this system.
In oporation (referenco " Schematic Representation
~/i of Nola I") a small samplo of iron oro slurry is recirculated A'
through'the activato call and count cell for five minutos.
It can them be dumped. cither into a wast'e line or back into the product lino.
None of the activated material is ever released to any area that directly connects to any life support chain.
The iron oro slurry has as its principal constituents Fb 0 23 (60-70%) and,'10
( 3-20%).
Tablo I lists some data on the more 2
prominent activation reactions possible.
Considor that in
' operation we put in 100 grams of iron oro for a five minute irradiation every cycle.
For neutron irradiations of this
\\
type, the formula Nn os where A = Activity in curies f
A" (3.7 x 1010) n = Neutron flux g
8 = Saturation factor - (1-e-At)
N = Number of targot atoms available l
o = Activation cross section O
E l
i
O P-n Ele =ent Isotope Activated Type of Reactilon Activation Product Half-Life Ga =a-Ray Energies and Abundance and Cross Section Threshold Nuclide of (MeV) and at 14 MeV (nb)
(MeV)
Activity Relative Abundances 16 0
0 (99.8%) ~
(n,p),40 10.0
~ N 7,y4 aec 6~1, 7 1~-
2 Si Si (92.2%)
(n,p),160 3.8 A1 2 3 min 1 77 Si S130 (3.09%)
(n, y), 110
- 31 S1 2.62 hrs 1.26 ( O.1) 54 (5.82%)
(n,y), 2500
- 55 Fe Fe 2 7 yrs o.006 Fe 54 (n,p),375 2.0 En 290 days cr X-rays 56 Fe -
Fe (91 7%)
(n,p),110 39 Mn 2 58 hrs 0.845 (100) 1.81 (30) 2.13 (20) $
e e
Thed Cross' section
~
TABLE I O
O
9-o l
[
will estimate the amount of activity produced per irradiation
{'
within an order of magnitudo.
However, experimentally it has boon dotormined, in a five minuto count. poriod, that the Si 0(n,p) Al reaction pro-8 duces about 1.5 x 10-2 Ci of A1 in the system.
28 All the other reactions, except FeS4(n,y)Fo have comparablo 5
cross-sections, but will not produce as much radioactivo material as the abovo reaction because their half-livos are long compared to the irradiation time.
Therefore, the satu-ration factor for these reactions is much smaller.
In summary, we proposo that no significant hazard oxists either to employcos or the gonoral public, in the routino rolcase of the amounts of radioactivo material produced in this system.
We, therefore, will not mako routino monitoring or sampling par,t of
- ()
our safety program.
s' em e
G s
O 8
e s
0 0
0 6
C e
e
- es.....
HP-RS-104
.. Texas Nuclear Pago 1, Issue 2 March 5, 1973 LEAK TEST PROCEDIjRE - QT/lK The gaugo should not be dismantled or disassembled in order to leak test.
Testing of tho external scams, flanges, and end plate is ade-quato.
Each kit is designed and supplied to test ono., gauge.
1.
If tho gaugo has a movablo shutter, position the shutter actua-tor to the closed position.
In tho event that the shutter actuator is frozon, or appears damaged, notify immediately:
Texas Nuclear Health Physics Department (512) 836-0801, Ext. 256.
2.
Removo the two cotton-tipped applicators and the bottle con-taining the wash solution.
3.
Moiston the applicators in the solution and wipe the sourco' holder surfaces, around seams and bolts, whero contamination is most likely may bo in a sma,to appear.
The radioactivo material itucif ll, powder-like form and if the stool encap-sulation fails, the matorial can appear on the exterior of
.(m),
tho sourco holder at placos whero unwolded scams occur, around shaft bushings, or around bolt panotrations.
A drawin onclosed, or comments under " Additional Instructions",g, if if any, will assist one in defining the areas to wipe.
4.
After wiping, place the applicators in the bottle (cotton down) and break the wooden stems off against the bottlo edge so that the top can be rescaled.
Caro should be taken not to touch the cotton end of the applicators with the fingers following the wiping operation.
5.
Place the bottlo containing the cotton tips back in the mail-ing tubo, after securely scaling the bottle.
Identify the
. device tostod, either on the onclosed drawing, or on a.,.
separato page.
6.
Place the information shoots back in the mailing tubo and rescal.
7.
Use the self-addressed labol to return to Texas Nuclear.
e C
O e
9 e
e I
HP-RS-104 l
Leak Test Procedure - QT/lK Pago 2 NOTES Upon roccipt the applicators will be counted on instrument have a demonstrated sensitivity and accuracy of 1.02 x 10 g th'at pcitS%
for Cs-137, and approximately the same consitivity for other
[
energetic gamma emitters.
If the applicators are found to be free of contamination, a notico will be sont via mail in the form of n'loak test cortificato.
If the applicators are found to con-tain significant amounts of radioactivo material, an cmorgency a
' notification will be sent, via tolophone or tologram, advising that the unit must be taken out of servico and what additional actions should be taken.
The Post offico Dopartmont regulations prohibit the shipment of radioactivo matorial through the mails when the lovel of gamma radiation at the outor surface of the mailing tubo exceeds 0.5 milliroentgens por hour.
Thorofore, the mailing tubo should bo surveyed with an appropriato radiation detector, when such is availabic, prior to mailing.
If the lovels excoed 0.5 milli-roentgens per hour, notify Texas Nuclear for further instructions.
(',._
If after reading the instructions contained there is still somo question as to proceduro, please contact Texas Nucloar Health Physics beforo proccoding.
Additional instructions:
e e
a 9
e l.C:.'
.,o
- (o)
\\}
in CELL CllECK AND REMOVAL PROCEDURE C
This proceduro in utilized only after the counting data loads one to believe that como abnormality han occurrod to the sourco or irradiato. coll.
1.
The operator should shut off the input of, slurry, actuato
,e the main valvo, and open the water fluoh valvo to cican the nystem.
2.
Ldak test the cource according to the Leak Test Proceduro, and do not proccod on coll removal until the ronults of the tout are rocoived.
3.
If leak toot resulto are negativo, proceed with call removal an outlined below and in the noction titled "Romoval of Activato cell (roforenco Inner Sourco Shiel.d
(
Ancombly Drawing).
4.
Cover the working arca at the top of the tank with absorbent material.,,
- 5.
- Position a plantic pan nearby no that tho encapsulation call can bo lifted up through the oil and placed in the pan with no upillago.
Handlo the call with rubber gloven which can bo canily wanhed.
6.
Moanuro the radiation exponuro raton from tho encapsulation call to incuro that the icvoin aro low enough to procood.
For examplo, exponuro raton at tho nurfaco of the call up to 25 mR/hr uhould bo conaldorod'acceptablo.
7.
The compononto of tho encapsulhtion call annombly should bo monitored an dinanuenbly proccoda, and all parto nhould bo (l
cleaned thoroughly an noon an practicablo.
I
/
g b
g o
JUN 0419M LEAK TEST OF ACTIVATION ANALYSIS SOURCES TILDEN MIN' C..
a The system should not be dismantled to leak test the source.
1.
With the cource and cell in position, dip out two to four ouncos of chield fluid from down near the top of the cell, and!pourit'intothecamplobotticsuppliedwiththetest kit;j close and 0.ock the top cover plato.
2 Cap,the bottle and tape the top closed to provido a positivo scal.
3.
Eill in the provided card with full identification, including model number, serial number and dato.
4.
Placo the bottle in the mailing tubo and cond as followu Texas Nuclear Division
('<
P. O. Box 9267 d
!!calth Physics Upon recolpt of the oil camplo, the fluid will bo diluted in !! 110 2
3 (1-normal) and than filtored.
It will then bo ovaporated to drpncan and counted for alpha contamination.
If found froo of contamination, a notico will bo cent via mail, in the form of a lonk tont corti-ficato, that the courco in look frco.
If the oil in found to con-tain detectablo amountu of alpha contamination, notification will bo acnt, via tolophono or tologram, advioing that the oil bath cover chould not bo oponod and that an additional lonk tant namplo in to be taken and cent by air to Yoxan tiuclear for analycio.
If the accond complo containn alpha contamination, notification vill be cent advicing that, Texan tiuclear porconnel will bo cont to removo the courco for roturn to the manufacturor.
Under no circumntancco in the chiold to bo opened during thin period of timo.
C' b
.o o.
g
SUMMARY
OF RADIATION SAFETY PRECAUTIONS
('/
NOLAlDonsity System A.
l 1.
Cs-137; 500 mci in a load-filled sourco head.
I 2.
Radiation survey provided at installation and nood not be repeated.
l 3.
Leak test once ovary throo years.
(QT/1K)
- l 4.
Insure that the sourco shutter is closed during all maintenanco on the cloctronics and leak testing.
B.
NOLA Activation Analysis Syntom 8
1.
Pu-230-Do omitting 1.1 x 10 n/ soc.
I 2.
Radiation survoy provided at installation and nood not be reponted.
4 3.
Leak Test onco ovary six months.
(Loak Testing of Activation Analysis Sourcon)*
4.
Radiation fields under normal conditions of use are
( -)
very low.
5.
The sourco is affixed to a plato at the bottom of the oil bath.
6.
Loss of the antire water shiold does not precludo e
repair with the source in placo.
The maximum radiation levoln without the water shiold would be approximately 15 millirem por hour at the tank.
7.
clavoland cliffn personnel cannot remove the source.
8,.
The slurry loop is p1wa prior to any shutdown. ys to be flushed with water 9.
Removal of the irradiato call requires the handling of slightly radioactivo matorialo.
Tho activation products built-up will not croato radiation fields that are high in terms of nignificant dono.
Ono should be awaro of them and, if appropriato inntrumentation in availablo,
, monitor thono fieldo during handling of the irradiato coll.
Cloven should bo worn during handling and the handn wached upon completion.
All componento should be olenned and ntored away from occupied arcan until fu roansombly.
Familiarizatlon with tho " Call Chock and
(
Removal Proceduro" in advined.
l l
e 2
O g
76-/7;2)
Gk ( x an d, ) j e6 9) m t ajr' N
dMm/
REGULATORY FILE CY,,
I C. A. DAWE. M ANAes s. MscHeeam MINE.
W.L 000 A. MANAet.
E. A C A DevsLoPMEhN J.D P ON e 486 9 8 k7,.
s 6h>
om, 14, 1974
- l
[7 i
hs 3
Jyt,,,
t> &
s.
i I QN 5
of
%\\
Director of Licensing i
U. S. Atomic Energy Commissioni ~ b
+
, g%
3 Washington, D.C. 20545 Y%
Dear Sir:
The enclosed information, submitted in triplicate, is to support our request for the issuance of a Special Nuclear Material License for a Texas Nuclear Corporation NOLA I Silica Analyzer. This gauge contains appro;imately 2.9 grams Plutonium 238 as an oxide mixed with 15.2 grams of Deryllium and is manufactured by Monsanto Research l
Corporation, Dayton, Ohio.
It also contains a Cesium 137, 500 millicurie radiation source. The license application for this portion of the analyzer is attached separately. We have included a check for $50.00 to cover the application fee for.
Special Nuclear Materials License.
Drawings and description of system are enclosed, in triplicate, for your reference as outlined in the table of contents.
NOLA I Silica Analyzer is to be installed at the Tilden Mine, Tilden Township, Marquette County, Michigan, as shown on enclosed drawing 48-A-102.
Manager of the Tilden Mining Co. is Cleveland-Cliffs Iron Co., an Ohio Corporation, tith offices in Cleveland, Ohio and Michigan offices in Ishpeming, Michigan.
Principal officers are:
President -
S. K. Scovil Senior Vice Prostdont -
J. S. Westwater Vice President - Operations -
E. D. Johnson General Manager, Michigan Mines -
G. A. Dawo All are U. S. Citizens.
The installation calibration and initial checkout of this device will be carried out with the assistance of Texas Nucicar Corporation Engineering Personnel.
Upon completion of the installation, the equipment will be operated by our personnel.
At no time, will they be pennitted to handle the radiation source. The equipment will be operated in the mannor prescribed by the manufacturer.
If, at any timo, difficulties should arise which require opening of the sourco enclosure, the assistance of Texas Nuclear personnel will be requested.
Q'&AWY l5Q nc q (9
O O
i Director of Licensing i
June 14,1974
-.Page Two The responsibility for health physics will rest with our Mr. Carlo Maki, who will be instructed in the proper use and nuclear safety aspects of the gauge by Texas Nuclear personnel.
I The gauge location and surrounding area will be posted in accordance with requirements under Title 10. Part 20. We propose to leak test this source using the procedure i
entitled " Leak Test of Activation Analyses Sources" at least once every six months.
l In the event the use of'this system is discontinued, the removal and disposal of I
l the radioactive material will be handled by Texas Nuclear.
l Very truly yours, THE CLEVELAND-CLIFFS IRON COMPANY t.) l%b D Carlo W. Maki Instrumentation Engineer CWM/CUK:b1m i
l Applican t..............
Check No. 7 Amoun t... '. f' 0.4[......
1 D.......h....
oat. a en.. h... u : C.2......
Oata et u;i h W..?..'..'.
~ U......
.7./'....
Rectiud Py.... !.U.Y. ! $ d T
W
" fne..
mens 6 f,W i
l l'.
O r
APPCilDIX j
l TABLE OF CONTENTS i
Item l
Drawing - Pu238-Be Source Capsulo Drawing - Neutron Source Shield Drawing - Inner Source Shield Assembly l
Leak Test of Activation Analysis Sources Drawing 48-A-102 Showing Laboratory Arrangement Summary of Radiation Safety Precautions N0LA I Silica Analyzer
[
Schematic Representation of NOLA I t
NOLA I Density Gauge N0LA I Irradiator r
?
b I'
e h
L :.
O O
LEAK TEST OF ACTIVATION ANALYSIS. SOURCES
?
s l
The system should not be dismantled to leak test the source.
I l
1.
With the source and cell in position, dip out two to four ounces of shield fluid from down near the top of the cell, and pour it into the sample bottle supplied with the test I
kit.
Close and lock the top cover plate.
2', cap the bottle and tapo the top closed to provide a positive seal.
3.
E111 in the provided card with full identification, including l
model number, serial number and date.
4.
Place the bottle in the mailing tube and send as follows:
7 Texas Nuclear Division P. O. Box 9267 Austin, Texas 78766 l
Attn:
Health Physics i
Upon receipt of the oil sample, the fluid will be diluted in H NO 2
3 (1-normal) and then filtered.
It will then be evaporated to dryness and counted for alpha contamination.
If found free of contamination, l
e notice will be sent via mail, in the form of a leak test certi-ficate, that the source is leak free.
If the oil is found to con-tain dotectablo amounts of alpha contamination, notification will i
be sent, via telephone or telegram, advising that the oil bath cover l
should not be opened and that an additional leak test sample is to i
be taken and sent by air to Texas Nuclear for analysis.
If the second sample contains alpha contamination, notification will be
, sent advising that Texas Nucle.
ersonnel will be sent to remove the source for return to the manufacturer.
Under no circumstances is the shield to be opened during this period of time.
l l
t l
l l
I l
i l
152ll l
i o
o
SUMMARY
OF RADI ATION SAFETY PRECAUTIONS A.
NOLA Density System 1.
Cs-137; 500 mci in a lead-filled source head.
2.
Radiation survey provided at installation and need not be repeated.
(QT/lK) * ' [h ?y !/ c ys a 3.
Laak tost once ovary throo years.
4.
Insure that the source shutter is closed during all maintenance on the electronics and Icak testing.
B.
NOLA Activation Analysis System 8
1.
Pu-238-Bo emitting 1.1 x 10 n/ soc.
2.
Radiation survey provided at installation and need not be repeated.
\\
3.
Leak Test once ovary six months.
(Loak Testing of
(
t Activation Analysis Sourcos)*
4.
Radiation fields under normal conditions of uso are very low.
5.
The sourco is affixed to a plato at the bottom of tho oil bath.
6.
Loss of the entire water shield does not preclude repair with the source in place.
The maximum radiation levels without the water shield would be approximately 15 millirem por hour at the tank.
7.
clavoland Cliffs personnel cannot renovo the source.
O.
The slurry loop is p1 ways to be flushed with water prior to any shutdown.
9.
Removal of the irradiato call requires tho handling of alightly radioactivo materials.
The activation products built-up will not creato radiation fields that aro high in terms of significant dono.
One should be aware of l
them and, if appropriato instrumentation in availablo,
, monitor thono fields during handling of the irradiate cell.
Gloven should be worn du*ing handling and the hands washod upon completion.
sti componento should l
be cleaned and stored away from occupied arcan until reassembly.
Familiarizatlon with the " Coll check and Removal proceduro" is advised.
1528 i
,_.,m_.
~
m I
DENSITY GAUGE
- d.
j
]
'k G
W RCE A
- 4) gg l [
sm R
f, x
?
I 5
SWRRy L
.j HAE2JEG
-i g el_~ ~ '
N f) b>l!!ji g
A J"
'1 e[
g!
, 4 ;l:'- !
COUNTER CONTROL AND DATA t
ACQUISITION UNIT i
f NOLA I SILICA ANALYZER i
s l
~
l
a SLURRY HANDLING SYSTEM r------------------------,
d l
N UT IRRADIATOR PUMP
/
l p
TIME m
RECIRCULATE C
o
(
TWO-WAY O__
SEQUENCE y
g O_ ~
CONTROL VALVE
/
~D
~~~
~O
- - ~
- a CHARGE-FLUSH NEUTRON
-p_.___ O DENSITY bUE SOURCES l
u DENSITY GAUGE DElt.cTOR I'~~~
~~3 s
f; ELEC I
~
'g
_w
L a
~~_
D G~~~
- O 7-RAY l
q> DATA y
g O
SOURCE K27
- O COva:TER+ :nTERrACE
~
~
\\
\\_/
\\
e
\\s PRINTER +
b T
c 1" '
T h'
DATA ACQUISITION l
pETECTOR SCHEMATIC REPRESENTATION OF NOLA I
~
1 SLURRY LOOP
~
TUBIN G NAI(TR) y RAY DETECTOR 7N
~
su
.)s; s
4>s
/
s
/-
/.Ha, $dj9 j3
~f-x
~
g TUNGSTEN NUCLEAR CHICAGO COLLIMATOR g
MODEL 5176 LEAD DENSITY GAUGE HEAD COLLIMATOR
~
NOLA I DENSITY GAUGE m_
a
.M m
OIL
/
i
~:
'N A
Hi D'
[
l i'
k N
q es N
g f
d[ ~ il b 7 '
_ -]
p>l m.,3 s.-
[
s-i L, 5:U =*
t b'.,
~
c NEUTRON l 7
'\\*3., l,f'-
SOURCE y
ENCAPSULATED \\
ACTIVATION
\\
g CELL x
l N
/
SOURCE
\\
/'-
TANK
\\
/.-
\\ xx/
-s NOLA I
lRRADIATOR
.