Outline Drawing—Front and Rear Panels, X90 Gamma Switch ........................................
Outline Drawing—NEMA Type 4 Enclosure ......................................................................
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Warranty
workmanship under normal conditions of use and service, and will repair or replace any component
found to be defective, on its return, transportation charges prepaid, within one year of its original purchase. this warranty carries no liability, either expressed or implied, beyond our obligation to replace the
unit which carries the warranty.
Ronan warrants equipment of its own manufacture to be free from defects in material and
1.0 GENERAL DESCRIPTION
The Ronan Series X90 Point Level Monitor economically
and reliably solves many process problems in which
noise, temperature, abrasive or corrosive conditions
preclude the effective utilization of sonic, capacitative,
float or other techniques. This is a non-contact system.
Normally, a small Cesium-137 radioisotope source is
housed in a lead-filled shielding enclosure known as the
source holder. This holder is equipped with a shuttering
mechanism and the means for containing the radiation
and collimating or directing the radiated energy toward
the sensor, which is directly opposite the source along a
line or level to be measured. Radiation in all directions is
attenuated to a safe value by the lead shielding. The
source holder is mounted on or adjacent to the vessel
whose content it is desired to monitor.
When the source holder shutter is opened, radiant
energy is directed toward the sensor. In the absence of
the process, this sensor sees only a small amount of
radiation but, when the process is present, a large
percentage of this radiation is absorbed. This absorption
of radiation by the process causes a change in the
radiation at the sensor. When this occurs, a relay
contact signals that the level change has been observed.
The passage of radiant energy through the process
causes no contamination and cannot make the process
or container walls radioactive. These systems may be
used anywhere, including the food processing industries.
For most applications, all components of the system are
externally mounted. Therefore, installation is simple and
requires no major mechanical modification or down-time.
The standard Ronan Model X90-301(V) gamma switch
uses Cesium-137 as the source of gamma rays.
Cesium-137 is a 0.66 MEV gamma ray emitter with a
half-life of 30 years. The radioisotope material is sealed
in a double-welded, stainless steel capsule. The source
type and strength (activity) supplied depends on the
individual application, and is printed on the yellow and
magenta caution label affixed to the 3 source holder.
The standard source holder is lead-filled and equipped
with a two-position ON/OFF shutter mechanism. The
handle and shutter mechanism can, by means of a
combination padlock, be securely locked in the OFF
position during shipping, installation, storage or processdown intervals.
Well sources are supplied with actuator rods, which can
be used to extend the source into the vessel or retract
the source into the storage source holder.
CAUTION: Any malfunction of the source holder must
be immediately reported to Ronan Engineering for repair
or replacement of the source holder. Under no
circumstances may the source holder be taken apart.
Should it be necessary to ship the source holder back to
Ronan, contact Ronan Engineering for detailed shipping
instructions.
A Geiger-Mueller tube is used as the sensor for
detecting the gamma radiation. The G-M tube consists
of a gas-filled cylinder with a central anode. The anode
is connected via a high ohmic resistance to a dc voltage
of 500 V. Conduction occurs when the gamma radiation
ionizes the gas in the tube. Each ionizing event
produces a pulse, the rate of these pulses being
proportional to the field strength of the ionizing radiation,
i.e., incident field intensity. The output of the G-M tube
is processed by an electronic circuit in the X90-301(V)
module and the material level is indicated by either an
ALARM or NORMAL signal.
_____________________________________________
2.0 SPECIFICATIONS (STANDARD)
The X90 is a solid-state instrument available in two
designs. The Model X90 Detector with integral
electronics has a combined detector and switch
assembly located at the vessel. The Model X90-1004
Detector with remote electronics module may be fieldlocated or remotely located in a control room
Power Consumption: Integral: 7 watts per alarm
Remote: 7 watts per alarm point
Relay Output: Integral: DPDT 3 A at 30 VDC; 3 A at
120 VAC Remote: DPDT 3 A at 30 VDC; 3 A at 120
VAC
Analog Output: Remote: 0-1 V
Failure Alarm:
Integral: Included Remote: Included
Integral: Class I, Division 1,
Integral: -40° to 185°F
Integral: 37.4 lbs. (17 kg)
Time Delay Range:
20 seconds normal); jumper-selectable Remote: .05 to
20 seconds (10 or 20 seconds normal); jumperselectable
Display: Integral: LED status indicator Remote: LED
status indicator
Accuracy: Integral ± 1/8” Remote: ± 1/8”
All equipment approved by CSA.
—————————————————————————
Integral: 0.5 to 20 seconds (10 or
3.0 THEORY OF OPERATION
The Ronan Series X90 gamma switches provide an
alarm signal whenever the radiation field intensity at the
detector (G-M tube) changes by more than its
predetermined value. The variation in the field intensity
may be due to either a change in the level (at the limit),
or a change in the density of the process material in the
radiation beam path. In a typical arrangement, the X90
detects the level of liquid in a vessel when it has
exceeded a predetermined limit. The level limit is
defined by an imaginary straight line drawn from the
source to the detector.
Figure 1: Source and Detector
When the feed valve is open, liquid is fed into the vessel
and the liquid level rises. The liquid level will rise until it
interrupts the gamma ray beam. There is then a change
in the field intensity at the detector due to absorption by
the process of some of the energy present in the beam,
and the instrument puts out an alarm signal in the form
of a relay contact changeover. This signal may be used
to close the feed valve and/or activate an annunciator.
As the liquid is used from the vessel, the level will fall,
thus again exposing the detector to the gamma radiation
and the feed valve will be opened when the contacts
revert to normal.
This is an example of a high limit switch, i.e., the process
level is not allowed to rise above a certain limit.
Conversely, the source and the detector may be lowered
to below the liquid level and the system functions as a
low limit switch, in which case the system will produce an
alarm when the liquid level falls below this low limit. The
liquid itself may be under pressure at high temperature
or even corrosive, but its characteristics will not affect
the switch, since the system components are outside of
the vessel.
A time delay based on the measurement controls the
interval between radiation level change and alarm. A
hysteresis band about the required level prevents
fluttering and spurious alarm situations.
3.1 Optional Gaging Configurations
3.1.1 Model X90-1004 Remote Probe: The Ronan
Model X90-1004 Remote Probe (located on vessel)
with the X90-301(V) switch electronics may be
located in a general purpose or Division II location.
This is the most widely used configuration. The
X90-1004X is a high-sensitivity tube, which may be
specified for very weak fields (0.1 mR/hr. or less).
3.1.2 Model X90-1005 Integral Switch: The
Ronan Model X90-1005 Integral Switch in a Model
X90-1001XP housing is usually specified when the
X90-301(V) switch electronics cannot be located in
a general purpose or Division II area. It may be
used when the vessel is easily accessible for
calibration and maintenance.
The Model X90-1005 contains the G-M tube sensor
and switch electronics on a single chassis and is
mounted on or just off the vessel wall.
—————————————————————————
4.0 FUNCTIONAL OPTIONS
4.1 High-Limit Process Alarm
The Process alarm relay will change over when the
level of process material rises above the set limit.
4.2 Low-Limit Process Alarm
The process alarm relay will change over when the
process level falls below the set limit.
4.3 Failure Alarm
In the case of the high-limit switch, under normal
conditions the G-M tube receives full radiation and
produces an output. This output will fall, producing
an alarm when either the radiation is interrupted by
the process level rising to above the set limit or the
G-M tube or its power supply fails. However, if the
tube or power supply fails, a failure alarm will be
actuated, indicating the problem is in the unit. If
the tube output does not indicate a minimum
background value (due to a malfunction in the G-M
tube or its power supply) the process (and failure, if
used) relay automatically changes over, indicating
an alarm condition.
The failure alarm will occur anytime the output from
the tube is zero.
—————————————————————————
5.0 TIME DELAY OPTIONS
The basic time constant is 0.5 seconds to 40 seconds,
depending upon the span setting. Additional time delays
available are 0.1, 5, 10 and 20 seconds.
For most applications, the 0.1 second jumper is used. If
false alarms occur, the time delay should be increased.
The delay is selected by a plug-in jumper located on the
electronics chassis printed circuit board.
5.1 Relay Contacts
Two Form-C (SPDT) contacts are provided.
Contact ratings are 3 A at 30 Ddc or 120 Vac
resistive. Other forms of contacts may be provided
on request.
If both sets of contacts are to be used for the
process alarm relay, jumper A10, B-11 and C-12
(located on the X90-301(V) printed circuit board or
X90-1005 printed circuit board for the integral
version.) For the integral Model X90-1005, 10A
contacts are provided as standard equipment.
If one set of contacts is to be used for a failure
alarm relay, D10, E-11 and F12 are jumpered.
—————————————————————————
6.0 CIRCUIT DESCRIPTION
The X90-301(V) and X90-1005 circuitry consists of a
stabilized ± 12 V and 500 V power supply, a voltage
integrator, comparator and logic alarms.
The output pulses from the G-M tube are fed through an
emitter follower to the input circuit. The pulses are + 12
V, 200 microseconds wide.
The G-M tube output is integrated and amplified by the
input circuit. The zero and span controls are used to
generate a 0 to 1 V output for low to high level
conditions.
This output is monitored using a simple VTOM across
the test points, AMP and TP GRN. A comparator circuit
will trip the relay circuitry at 0.9 V and reset at 0.2 V.
Jumpers on the circuit board are provided to make the
switch function as a high-level or low-level limit alarm.
Complete circuit schematics and wiring diagrams are
provided at the end of this manual.
7.0 INSTALLATION AND ELECTRICAL
CONNECTION—GENERAL
All equipment manufactured by Ronan Engineering is
carefully packaged and shipped to prevent shipping
damage. Any discrepancies between shipping contents
and invoice should be immediately reported to Ronan or
the Ronan representative.
All Series X90 system components (source holder,
integral switch and remote tube assembly) will tolerate
normal industrial vibration. However, in cases where
vibrators are attached directly to the vessel, the system
components must be mounted on adjacent building
framework or use special supports that provide a degree
of isolation.
When the axis of the G-M tube is placed parallel to the
surface of the process material and its side-facing
source, relay contact changeover will be obtained when
the set limit is exceeded by about one-half inch. When a
coarser level limit is appropriate, a broad band of about
five inches can be obtained by placing the detector axis
perpendicular to the surface of the process material. In
either case, an alarm is produced after the tube is
obscured from (or exposed to) the radiation from the
source.
Whenever possible, separate power sources should be
used for the X90 and the alarm circuit. With this
arrangement, the alarm will operate if the power to the
X90 is interrupted (provided, of course, the alarm circuit
has power available).
Local electrical codes must be followed for all wiring. All
conduit entrances should be sealed to prevent
condensed moisture or water from entering the
enclosures. The cable used to connect the remote G-M
tube should also be run through conduit. All explosionproof housing covers must be replaced when the system
is in operation.
7.1 Remote Probe (X90-1004)
The G-M tube with X90-1004 driver board is placed
in an explosion-proof housing. This assembly is
mounted in position at the required level or point of
measurement and connected to the X90-301(V)
module by a four-conductor, shielded cable
supplied by Ronan Engineering.
Refer to drawing number C-1369-K for wiring of the
remote detector assembly and refer to drawing
number C-1359-K for designation of terminals on
the X90-301(V) module.
7.2 Model X90GPE
The X90-301(V) modules are plugged into X90GPE
surface-mount, single chassis enclosures. Access
to input/output and power connections are from the
front, beneath a convenient, snap-on cover.
Connections are located in a separate
compartment of the chassis and removal of the
module is not necessary in order to change wiring.
Grommeted holes are provided on the top and
bottom surfaces of the chassis for cable entry and
exit. Overall dimensions are 7.25” high X 4.5” wide
X 5.75” deep (18.42 cm X 11.43 cm X 14.6 cm).
Refer to drawing number C-1359-K for terminal
designations for power wiring and hook-up to the
remote probe driver board.
7.3 Integral Model X90-1005
Refer to drawing A-1697-K for rear-panel input
power wiring connections and relay contact wiring
connections.
—————————————————————————
8.0 CALIBRATION CONTROLS
The following front-panel controls are used in the set-up
procedure.
ZERO CONTROL is used to provide a zero voltage
signal at TP-AMP with the process level below the point
of measurement, under conditions of maximum radiation
at the G-M tube.
SPAN is used to provide a + 1.0 voltage signal at TPAMP when the process level is above the point of
interest, under conditions of no radiation on the G-M
tube.
Three light-emitting diode (LED) DISPLAYS are
provided. These indicators will signal normal and level
alarm for process conditions and failure alarm.
The AMP TERMINAL is the output of the voltage
integrator. This output increases as the radiation on the
tube decreases and vice versa.
Calibration should be attempted only after all system
components have been securely mounted in position and
power and other connections made where required.
Check also that the correct jumpers have been installed
on the X90-301(V) or X90-1005 printed circuit board.
—————————————————————————
9.0 CALIBRATION—GENERAL
The output at the AMP terminal is a measure of level
present at the detector. This reading will be minimum or
near zero when the detector is fully irradiated (no
process) and the maximum or near 1.0 V when there is
process material between the source and the detector.
Therefore, for calibration any option, two voltage
readings are generated: 0.0 V with no process between
the source and the detector and + 1.0 V with process
between the source and the detector.
9.1 Calibration with Process Material
a) Switch on the power to the X90 and turn the
shutter handle on the source holder to the ON
position. Turn the SPAN control clockwise 20
turns; then 10 turns counterclockwise.
b) Lower the process level below the set limit and
adjust the ZERO control so that the AMP terminal
output is zero.
c) Raise the process level above the set limit and
again measure the voltage at the AMP terminal.
d) Adjust the SPAN control to obtain a reading of +
1.0 V at the AMP terminal.
After the switch has been calibrated using the
above method, the operation of the control relay,
NORMAL and ALARM indicators should be
checked by raising and lowering the process level
about the set limit. If all these operate as required,
the switch is considered calibrated.
9.2 Calibration without Process Material
a) Turn the source holder shutter to the ON
position.
b) Turn the SPAN control clockwise 20 turns; then
10 turns counterclockwise.
c) Take voltage reading at the AMP terminal.
Adjust the zero control to obtain an average 0.0 V
reading at the AMP terminal.
d) Turn the source OFF.
e) Adjust the SPAN control for an average + 1.0 V
reading.
f) Turn the source back ON for operation.
9.3 Time Delay
If false alarms occur, increase the time delay by
moving the delay jumpers on the printed circuit
board to a higher value.
9.4 Response Time
The response time of the amplifier is 0.5 to 40
seconds, depending on the SPAN setting.
Device
High limit switch
Low limit switch
Process alarm only
Process alarm and failure
alarm
Delays
High and G
Low and G
A-10, B-11, C-12
Failure relay and D-10, E-11,
F-12
Select one: 0.1 sec., 5 sec.,
10 sec., 20 sec.
Install
10.0 TROUBLESHOOTING
The X90 is constructed to require the minimum of
maintenance. Operated properly, it should not require
any maintenance for a considerable period of time.
Any necessary troubleshooting should start with the
power supplies. Ronan Engineering suggests that a
voltmeter with a resistance of at least 20 kohm/V be
used for measurement of voltages. Verify that the power
supplies are working before starting with the rest of the
circuitry. The operation of the main circuit may be
checked by adjusting the ZERO control to change the
amplifier voltage at the AMP terminal. Vary the voltage
and check the operation of the relay. Use the circuit
description and circuit schematic D-1357-K or D-1674-K
for reference.
If the relay circuit works properly using the ZERO control,
check the operation of the G-M tube with the source ON
and OFF to see if the tube responds.
For any major faults, we suggest the X90 be returned to
Ronan Engineering for service.
—————————————————————————
11.0 RADIATION SAFETY
The information in this section is intended for specific
licensees. The regulations and instructions pertain to
leak test and other procedures, which specific licensees
are authorized to perform. For general licensees this
section is included for information purposes only.
Most radioactive material used in gaging devices is
regulated by the United States Nuclear Regulatory
Commission (NRC). The NRC issues licenses to users
and manufacturers of gaging devices utilizing radioactive
materials and inspects sites where materials are used to
determine compliance with the terms of the license.
The NRC has issued rules on:
a) instructions to employees (10 CFR part 19);
b) the licensing of radioactive materials and devices (10
CFR part 30); and
c) radiation safety (10 CFR part 20).
During 1962, the NRC began entering into agreements
with individual states to transfer regulatory authority to
them. Known as “agreement states,” their regulations
closely parallel those of the NRC and are essentially
identical, except that the agreement states usually
regulate the use of all radiation-producing devices.
NOTE: Only those individuals specially licensed to
mount, repair, relocate and/or remove the part of the
gage containing the radioactive source may do so. Each
specific licensee should carefully read his particular
license to determine the exact conditions of his license.
Gamma-emitting radioactive material radiates
electromagnetic energy which is similar to light, except
that it readily penetrates opaque materials and is able to
pass through several inches of steel or other dense
material.
The ability to penetrate dense material can be used to
advantage in the measurement of process variables
such as density, level and thickness, where a change in
detected radiation indicates a change in process
variable.
Radiated energy is harmful to the human body when
absorbed at an excessive rate. For example, a glowing
incandescent lamp cannot be held in the hand without
causing severe discomfort or a painful burn. The hand
can be held close to the lamp for seconds, at a few
inches for hours or several feet away continuously. By
use of insulation surrounding the lamp or hand, the lamp
could be held indefinitely without discomfort or injury.
Radioactive energy and radiation is analogous to light
energy and radiation with the radioactive source taking
the place of the incandescent lamp. Permissible human
exposure to a radioactive source is dependent upon:
a) the number of millicuries of radioactive material in the
source (similar to the wattage rating of a lamp);
b) distance from the source;
c) amount of absorber between source and body;
d) amount of portion of the body receiving the radiation.
The term milliroentgen per hour (mR/hr) is a measure of
the radiation field intensity in air. W hen radiation is
absorbed by the body, the term rem or millirem (0.001
rem) is used. This distinction is necessary because not
all radiation affects the body in the same manner. For
gamma radiation, the millirem (mrem) is equal to the
milliroentgen.
The NRC limits the amount of radiation which a person
should receive to 1.25 rem per calendar quarter. This is
an average of about 100 mrem per week.
The 1.25 rem per calendar quarter limitation is a dose at
which there is no possibility of injury. However, since the
use of gamma radiation is relatively new, the history of
injury is not complete. Thus, it is wise to receive as little
radiation as possible. To guard against possible
overexposure and to maintain a record of personnel
routinely exposed to radiation, the NRC requires
monitoring of persons who are apt to receive more than
an average of 25 mrem per week or who are exposed to
a radiation field greater than 100 mr/hr. When personnel
monitoring is required, a record must be kept showing
the dose received. When records are kept, and if an
employee requests it, the employer must furnish a
written report of radiation exposure annually and on
termination of employment.
In the majority of Ronan installations, the source is
contained in a lead-filled source holder with an ON/OFF
mechanism. The holder is designed so that the radiation
field is 5 mR/hr or less at a distance of 12 inches from
the surface of the holder when is is in the OFF position.
When the source holder is mounted on the pipe or
vessel and turned to the ON position, the pipe walls,
process material and mounting bracket absorb most of
the radiation. Again, the field intensity is about 5 Mr./hr
at a distance of 12 inches from the surface of the gage.
Thus, a person would have to be within 12 inches of the
gage for 20 hours per week to receive 100 mrem. A
person would have to be within 12 inches of the gage for
five hours per week before he would be required to have
a personnel monitoring device, such as a film badge or a
dosimeter.
Long experience in the nuclear gaging industry with
hundreds of gages, where the source is contained in a
source holder, indicates that the dose received by
operators, maintenance personnel and supervisors
averages less than 25 mrem per week. Thus, for gages
where the source is contained in a source holder, it is
usually not necessary to provide any personnel with
monitors.
Whether or not monitoring devices are needed should be
determined at the gage site at the time of installation in
the form of an occupancy evaluation. Only those
persons specially licensed by the NRC or an agreement
state to install a radioactive device are qualified to make
an occupancy evaluation.
In some installations, it is impossible to mount the source
in a source holder. In these cases the source is usually
mounted in a source well. Installation of the source in
the well should be done as rapidly as possible. All
necessary equipment should be assembled prior to
opening the shipping box containing the source.
A trial installation using a dummy source is
recommended. A dummy source can easily be
fabricated from steel or brass using the outline drawing
of the source supplied by Ronan Engineering. When an
unshielded source is installed in a vessel or when it is
wipe tested, the radiation field is usually greater than 100
mR/hr. Thus, personnel monitoring in the form of film
badges or dosimeters is required. A record of the the
film badge or dosimeter reading must be kept on Form
NRC-5. Since records must be kept, the employer must
furnish to the employee, if requested, a record of the
employee’s radiation exposure annually and on
termination of employment.
Additional precautions are required when a gage is used
on a vessel large enough to permit entry of personnel.
With the source holder in the open position or when the
source is not removed from the source well, the radiation
field intensity inside the vessel can be high. A procedure
must be established so that personnel cannot enter the
vessel until the source holder is in the closed position or
the source is removed from the source well. The use of
padlocks on all man-way and access port covers is
acceptable. The key or combination for the locks should
be kept by the person responsible for radiation safety.
In some cases, when the vessel or pipe is empty, the
radiation field intensity of the outside of the pipe or
vessel will be such that personnel monitoring is required.
For installations using source holders, this problem can
easily be solved by turning the source holder to the OFF
position. For installations using sources in source wells,
where the radiation cannot be turned off, it may be
desirable to remove the source temporarily and return it
to its lead shielded shipping and storage container.
11.1 Field Intensity Calculation
The best method for determining the radiation field
intensity is by measurement with a survey meter.
However, the field intensity can be calculated fairly
accurately without a survey meter.
mCi k
D =
(d)
D = dose rate, mR/hr
mCi = millicurie value of source
d = distance to source in inches
k = constant 0.023 for AM-241
0.5 for CS-137
2.0 for CO-60
Suppose that for a certain installation the estimated
exposure time to the unshielded source is 10
minutes at an average body-to-source distance of
20 inches. The source is 10 millicuries of CS-137.
The dose rate would be:
And the dosage received would be:
2
rate Dose
(20)
dose Total===
1000 X
10 X 0.5
2
min 10
min/hr 60
The radiation field intensity
can be calculated from:
1000 X
400
5
mr/hr 12.5 1000 X
===
mrem 2.08 mR/hr 12.5
Figure 2:
Radiation Transmission CS-137 for Various Materials
9
Calculate the radiation field intensity at 12 inches
from the surface of the vessel shown in Figure 3.
Total distance = 12 + 2 + 10 = 24 inches
Dose rate for unshielded source:
10 X 0.5
rate Dose===
2
(24)
1000 X
476
5
Percent transmission of gamma radiation through
two-inch steel (vessel wall), 0.25-inch source well
wall = .18 X .83 = 0.517. Resultant field intensity =
8.6 X 0.517 = 4.45 mr/hr.
To estimate the dosage received by personnel
working in the vicinity of the source, the occupancy
must be known. Suppose that a man worked 24
hours per week within 12 inches of the vessel. He
would receive a dose in excess of 100 mr. He
would then require a monitoring device.
11.2 NRC Regulations
A current copy of the Title 10 Code of Federal
Regulations, Parts 19, 20 and 30 should be
obtained. These should be read thoroughly to
become familiar with the laws governing the use of
radioactive materials.
a) The “Individual User” listed on the “Application
for By-product Material License” (Form NRC-313) is
responsible for the source. If this person is
transferred or is changed to a position where he is
no longer responsible for the source, the license
must be amended prior to the assignment of the
mr/hr 8.6 1000 X
new user. [30.32, 30.33, 30.34, 30.38]
b) Use of the source is usually licensed for a
particular plant site. If the source is transferred to a
different plant site the license must be amended
prior to the transfer. [30.34 and 30.38]
c) A record of the initial radiation survey must be
kept for reference. [20.40 1 b]
d) Records of the periodic leakage test must be
maintained.
e) A label must be attached to the source holder,
or source well, stating the type and quantity of
radioactive material and the date of manufacture.
The label must bear the conventional radiation
symbol. An NRC-approved label is attached to the
source holder by Ronan Engineering prior to
shipment. For sources in source wells, and NRCapproved tag is placed on the source shipping and
storage contained. [20.203]
SOURCE HOLDER
SOURCE WELL
1/4” WALL
THICKNESS
SOURCE ROD
DETECTOR
SOURCE CS-137
10 MILLICURIE
10.00” 12.00”
304 SS
2” WALL
THICKNESS
Figure 3:
Dosage
f) The area in the vicinity of the source must be
posted with a radiation warning sign, if the radiation
field is greater than 5 mr/hr at a distance of 12
inches from the surface of the gage. [20.204a and
20.203]
g) Personnel monitoring is required when personnel
are apt to receive a dose in excess of 23 mrem/wk
or when they enter a radiation field greater than
100 mr/hr. [20.202a]
h) Whenever the source is to be discarded, it must
be returned to Ronan Engineering for proper
disposal. Ronan Engineering must be contacted
for detailed shipping instructions. [20.301a]
i) The regional operations office of the NRC must
be notified of any incident, such as a fire or
explosion, which involves the radioactive material
used in the gage. [20.403] (Ronan Engineering
should also be notified.)
j) If personnel monitoring is required [20.202a], a
record of the radiation exposure must be kept on
Form NRC-5 [20.401a and 20.401c] and, if the
employee requests it, written notification must be
given annually or on termination of employment.
[19.13]
k) If a person receives more than 1.25 rem per
calendar quarter, he must be notified in writing of
the exposure and the NRC must be notified.
[20.405]
l) A restricted area is defined in 10 CRF 20.3A(14)
and the permissible exposure to individuals in a
restricted area is given in 10 CFR 20.101. An
unrestricted area is defined in 10 CFR 20.3A (17)
and the permissible level of radiation in an
unrestricted area is given in 10 CFR 20.105(b).
Any area where an individual, if continuously
present, can receive a dose in excess of 2 mrem in
any one hour or where he can receive more than
100 mrem in any seven consecutive days must be
treated as a restricted area and access thereto be
under the control of the licensee.
m) Employees working in, or frequenting, a
restricted area must be advised of the restricted
area by posting a Form NRC-3 19.11(c). The NRC
regulations state that this form must be posted so
than employees can “observe a copy on the way to
or from their place of employment” in the restricted
area. Thus, Form NRC-3 could be posted at or
near the entry into the restricted area. If personnel
do not work in, or frequent, a restricted area, Form
NRC-3 need not be posted.
11.3 Periodic Leakage Test
Information about the periodic leakage test is
covered in Section 12.
11.4 Radiation Publications
For those who desire further information on
radiation safety and the handling of radioactive
material, the following publications are
recommended:
Radiation Dosimetery, Hine and Brownell
(Academic Press, Inc., 111 Fifth Avenue, New
York, NY 10003)
The following publications and National Bureau of
Standards handbooks are available from the
Superintendent of Documents, Washington, DC
98025:
Number Title
92 Safe Handling of Radioactive Materials
73 Protection Against Radiation from
Sealed Gamma Sources
11.5 Abandonment and Disposal
Abandonment or disposal is prohibited unless
transferred to persons specifically licensed by the
NRC or an agreement state. This means that the
gage cannot be abandoned, sold for scrap, or
placed in the trash bin. If the gage is no longer
needed, it must be shipped to a person or company
specifically licensed by the NRC or an agreement
state to receive the gage for disposal.
11.6 Prohibition of Operation
Operation is prohibited if there is indication of
failure of or damage to shielding or source
containment. If there is any damage to the gage,
or failure of the source rod mechanism, place the
source rod in the OFF position (if possible) and
telephone the field service manager at Ronan
Engineering (606) 342-8500.
Care must be exercised when uncrating the gage.
If the crate is damaged in such a manner that the
gage might be damaged, Ronan Engineering
should be contacted for advice. If the lock is
missing, broken, or not locked, do not uncrate or
mount the gage in position. Call Ronan
Engineering for advice.
11.7 Mounting and Start-up
Anyone may mount the gages in position on the
vessel or pipes, do the electrical wiring, and turn
the electrical power switch ON, if the source holder
is locked in the OFF position.
When mounting the source holder in position, take
the necessary precautions to assure that it is not
dropped or damaged. Refer to the outline drawing
of the source holder in the back of this manual
before mounting it in position.
Only a person specifically licensed by the NRC or
an agreement state is allowed to remove the
source holder from its mounting or to dismantle it.
After these preliminary services are performed, a
person specifically licensed by the NRC or an
agreement state must do the start-up of the gage.
This involves unlocking the source holder and
turning it ON; testing for proper operation of the
source holder and position indicator; making the
initial radiation field intensity survey; and initial
testing for leakage of radioactive material. This
specifically licensed person must determine that
the gage is installed in such a manner that
personnel working in the vicinity of the gage will not
receive a radiation dose greater than 0.5 rem/yr.
The gage is shipped from the Ronan factory with
the source holder locked OFF. The combination ill
be given only to the specifically licensed person
performing the start-up and placing the gage in
service.
a copy of the tag attached to the lock follows:
Figure 4: Warning Tag
Device shall be tested for radioactive leakage and
proper functioning of source actuator rod at
installation, at source replacement and thereafter at
no longer than three-year intervals.
11.8 Well Source Holders SA-4, SA-10, SA-15
11.8.1 Source actuator: The actuator should
always move freely. There will be some slight
resistance to movement due to bearing friction of
the gasketed filling, which keeps out moisture and
dirt.
Do not force the source rod actuator.
If a portable radiation survey meter is available, the
radiation field intensity can be measured at the
back of the detector housing. With the source rod
in the STORE position, the field intensity should be
measurable. When the source is placed in the
well, the field intensity should decrease.
11.8.2 Source insertion procedure:
a) Open shutter and pin open with lock pin.
b) Loosen CGB fitting at source rod.
c) Remove handle and attach source extender rod.
e) Push source rod until source bottoms out in
well.
f) Tighten CGB fitting over source extender rod.
11.8.3 Source retraction procedure
a) Loosen CGB filling.
b) Pull source handle back until source rod locates
inside source tube. Source will hit positive stop
inside holder.
c) Push shutter to OFF. Lock with lock pin or
padlock.
d) Remove extender rod.
e) Remove handle from extender rod and attach to
source rod.
11.8.4 Wiping the test points: A wipe test and
radiation survey must be made before the source is
installed onto the vessel wall and before the source
is inserted into the well. The radiation protection
officer (RPO) or licensed personnel must supervise
the installation, source insertion and retraction.
The RPO must also classify the area based on the
radiation survey and personnel occupancy in the
vicinity of the gage.
The RPO must write control procedures for
personnel not to work or occupy the area around
the gage when the process is down, maintenance
on the vessel is performed, or when the vessel is
empty.
Anyone following the instructions of a leak test kit
may perform the wiping procedure, but only a
person or company specifically licensed by the
NRC or an agreement state may do the analysis for
radioactive material.
Using a cotton swab, wipe around the source rod
extending out the top of the source holder and at all
seams as shown in Figure 5. These areas are
most likely to be contaminated if the source leaks.
Do not touch the cotton-tipped end or allow it to
touch other objects, as this would spread
contamination if a leak is present.
After making the wipe test, replace the cotton swab
in the vial with the cotton-tipped end at the bottom.
Replace the cap on the vial, place the vial in the
shipping tube and replace the top on the shipping
tube. Send to: Ronan Engineering Company,
8050 Production Drive, Florence, KY 41042.
11.9 Standard Sources SA-1, SA-8
11.9.1 ON/OFF mechanism: To test the ON/OFF
mechanism, move the handle back and forth
several times between the ON and a OFF
positions. The handle should always move freely.
There may be some slight resistance to movement
due to bearing friction.
Do not force the handle.
If a portable radiation survey meter is available, the
radiation field intensity can be measured at points
around the detector housing.
11.9.2 Wiping the test point: Anyone following
the instructions of a leak test kit may perform the
wiping procedure, but only a person or company
specifically licensed by the NRC or an agreement
state may do the analysis for radioactive material.
Using a cotton swab, wipe around the rotor shaft on
the top of the source holder and at all seams, as
shown in Figure 6. These areas are most likely to
be contaminated if the source leaks. Do not touch
the cotton-tipped end or allow it to touch other
objects, as this would spread contamination if a
leak is present.
After making the wipe test, replace the cotton swab
in the vial with the cotton-tipped end at the bottom.
Replace the cap on the vial, place the vial in the
shipping tube and replace the top on the shipping
tube. Send to: Ronan Engineering Company,
8050 Production Drive, Florence, KY 41042.
Figure 5:
Wiping the Test Points (Well Sources)
11.10 Mandatory Reporting
Loss, theft or transfer of this device and failure of or
damage to the shielding or the source containment,
must be reported to the NRC or an agreement
state.
In addition to notifying the NRC or the agreement
state agency, Ronan Engineering should also be
notified, so that proper help can be provided.
If the gage is involved in a fire or explosion, the
area around the gage should be barricaded or
roped-off until the situation can be evaluated by a
specifically licensed person. Telephone Ronan
Engineering at (606) 342-8500.
Figure 6: Wiping the Test Points (Standard
12.0 LEAK TEST PROCEDURES FOR
SEALED SOURCES
12.1 Ronan Leak Testing Service
The NRC requires that all sealed sources be tested
for leakage at specified intervals. Only Kr-85,
tritium and certain sources of very small activity (10
CFR 30.18a) are exempted from leak testing.
Ronan Engineering provides for users’ convenience
and safety the “Leak Testing Service.” The leak
testing procedure detailed in these instructions
applies only to the Ronan Model WK Leak Testing
Kit supplied with the Ronan Leak Testing Service.
The Ronan Model WK Leak Testing Kit is intended
for use on all sealed sources that are not exempt
from testing.
This service may be purchased from Ronan on a
contract basis for five years when wipe testing at
six-month intervals is required or on a one-time
basis in the case of three-year wipe test intervals.
The service must be purchased for each individual
source. If the service is retained, Ronan will send
the required number of leak test kits, consisting of:
a) A cotton swab (“Q-tip”) saturated in radiac
wash, contained in a small plastic tube.
b) Special instructions on its use.
c) Leak test forms.
After the sealed sources have been wiped by the
materials, issue a report based on the results and
forward a copy of the results to the customer
immediately.
12.2 Using the Leak Test Kit:
For instructions on using the Leak Test Kit see
section 11.8.4 for well sources or section 11.9.2 for
standard sources.
Return the shipping tube, prepaid, via United
Parcel Services (UPS). Do not send the shipping
tube via conventional mail, as postal regulations
prohibit mailing of radioactive material in this form.
Upon receipt of the wipe, Ronan will perform a
sensitive analysis to determine the presence of
radioactive material. If the wipe is contaminationfree, a notice will be sent via mail that the source is
leak-free. If radioactive material exceeding .005
microcuries is detected on the wipe, an emergency
notification will be sent via telegram or telephone,
advising that the source holder must be taken out
of service and sent back for repair. The emergency
notification will contain detailed instructions for
removal and shipment of source holder.
Ronan will maintain records of each leak test
analysis performed. The records will include the
name and address of the customer; the date the
sample was collected; the individual collecting the
sample; the person performing the analysis; the
date the analysis was performed; the unique
identification of the source being tested; the
radioactive material and mass number contained in
the source; and the results of the test expressed in
PARTS LIST—SERIES X90 POINT LEVEL MONITOR
X90-1004 or X90-1004X Probe
Item
1 1 R1 RC20GF105J Resistor, Carbon, ½ W, 5%, 1.0 Meg Allen-Bradley