ML20059L802

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Voided Matls Licensing Action for License 34-00639-01 for Ohmart Corp.Control:386899
ML20059L802
Person / Time
Issue date: 03/02/1990
From: Patricia Pelke
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
NRC OFFICE OF THE CONTROLLER
References
386899, NUDOCS 9010010266
Download: ML20059L802 (72)


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///wo W -'Q jd February 3, 198 p n r gLs

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S. Nuclear Regulatory Commission Region III

-799 Roosevelt Road Glen Ellyn, IL 60137 RE:

Request for Approval--Model SH-F1 Source Holder g;

License Nos.134-00'639'9D and 34-00639-03G 6llzy.~..

Gentlemen:

Enclosed is our check for $1950.00 to cover safety evaluation of:

(31-996396-91*(Category 9A--S1600. 00),

Model SH-F1 '

amendment of license (Category 3B--S120.00) and amendment of license 34-00639-03G (Category 3J--S230.00).

The Model SH-F1 will be distributed-.to specific licensees as part.

of a' level gage, weigh scale, _or as-part of a densi'.y gage andito general licensees as part of a density gage.

The Model SH-F1 is-the smallest of the SH-F series and features a new " fireproof" design.

Photoaraohs The' enclosed photographs show the SH-F1 used as a--part of a level gage, as a part of a density gage and as part of a weigh scale.

Note from the photographs that the device can.be locked in the OFF position.

Outline Drawina.

An outline of a complete density gage using the SH-F1 is shown in drawing C-49349.

Note the " air gap shield" which prevents placing the hands close to the process pipe.

pevice Safety Performance Classification f,

The.-classification designation for the model SH-F1 source hold Ij310 percANSI Standard NS38 is ANSI 66-353-353-R2.

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USNRC 2

February 3, 1989 Radioactive Sealed Source one of the sealed sources that will be used in the SH-F1 is the Ohmart A-2102, CS-137 point source which has been approved-a.id been in use for many years.

The other sealed source that will be used in the SH-F1 is the Ohmart A-2100, Co-60 point source which also has been approved and been in use for many years.

Tvoical Environmental Conditions Are:

Temperature:

-400 to 60*C (-40* to 140*F)

Pressure:

Atmospheric Impact:

Accident conditions only Vibration:

Ranges from zero to mild corrosion:

Ranges from zero to highly corrosive vapor Fire: _

-Unlikely Explosion:

Unlikely Although the typical maximum operating temperature is 60*C, the source holder will withstand a continuous operating temperature-of 200'C-(392*F) with temporary operation up to 800'C (1472*F).

Above 140*C (482*F) the 0-ring seal will melt and allow moisture.

to enter the shutter /collimator cavity, but radiation-safety will not be affected.

Accident Conditions In a fire there would be no loss of shielding.

Thus, the source holder should remain intact--and retain the sealed source--up to a temperature just below the softening point of carbon steel which is about 1000*C (1832 F).

The sealed Cs-137. source, Ohmart A-2102, has zul ANSI classification of 77C66646, which specifies a temperature limitation ot 800*C (1472*F).

The sealed Co-60 source, Ohmart A-2100, has an ANSI classification of 77C63434, which specifies a temperature limitation of 8000C (14720F).

Explosion Ohmart cource holders of less rugged construction have been involved in explosions over the past years.

None of these source holders-has ruptured or broken apart, nor released the sealed source.

CONTR01 "" 8 6 8 9 9

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'USNRC' 3

February 3,.1989 Labels An existing radiation label is shown on the photographs.

A drawing of this radiation label is shown in drawing A-33739.

Note that the label is made of 28 gage, type 304 stainless steel etched 0.003 inch deep and filled with yellow and magenta enamel paint.

There are'two positions of the shutter: OFF and ON.

The indicating arrow on the recessed, rotating handle points.to-.the shutter positj o.

The OFF/ON label is made of 28 gage, type 304 stainless steel etched 0.003 inch deep and filled with enamel paint.

When-the density gage is distributed to general licensees, the labelshownindrawing,B-33568is, also, attached.

The radiation label, the "Ganeral I.icense" label, and the OFF/ON label are all attached with stainless steel drive screws.

The ON condition warning label, drawing A-22425, uses a pressure sensitive adhesive.

A warning tag, drawing A-25864, is attached to the padlock.

Proto*.voe The SH-F1 is a rugged fireproof design that can pass the following environmental performance testing:

a) vibration 0 through 50 cps at 0 through 1/16 inch displacement for 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />, b) impact--several hundred blows with 1/2 pound hammer c) temperature--800*F for 30' minutes d) OFF/ON control--operated several hundred times In addition, the SH-F1 successfully passed all tests described in-49-CFR 173.411, 173.412 and 173.465 for Type A packaging.

Radiation Surveys

-Radiation surveys were conducted in accordance with the procedures described in NBS Handbook 129, American National Standard N538.

Level Gace l

When used as part of a level gage, drawing D-49331 shows the l

radiation field intensity at distances of 5 cm, 30 cm and~

100 cm for the source CN (shutter open) and the source OFF (shutter closed).

CONTM1. N0.8 6 8 9 9

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USNRC 4

February 3, 1989 Ueich Scale When used as part of a weigh scale, drawing D-49350 shows the radiation field intensity at distanceslof 5 cm, 30 cm

-and'100 cm for the source OH (shutter open) and the source OFF (shutter closed).

Density Gace When used as part of a density gage, drawing-D-49345 shows the radiation field intensity around the complete density gage at distances of 5 cm, 30 cm and-100 cm with the pipe empty.

The survey is shown for the maximum nominal pipe size--6 inch diameter.

The minimum nominal pipe size is 1-1/2 inch diameter and the field intensities are essentially the same.

. Maximum Activity Maximum activity is determined using the criteria of 100mR/hr, maximum, at 5 cm from the surface of the-device and SmR/hr, maximum, at-30 cm from the surface of the device.

For.the SH-F1 used as part of a weigh scale (2ee D-49350), the normal activity used for measurement is 50 mci, If a higher mci would be used, the bottom of the detector would have shielding added to maintain 5mR/hr at 30 cm.

Therefore, based on all other data points, the maximum activity would be:

of Cs-137:

5/3.3mR/hr

  • 85 mci = 128 mci ofico-60:

5/1.9mR/hr

  • 3 mci = 7.9mC' For the SH-F1 used as part of a level gage (see D-49331), the maximum activity would be:

of Cs-137:

5/3.5mR/hr

  • 85 mci = 121 mci of Co-60:

5/1.9mR/hr

  • 3 mci = 7.9 mci For-the SH-F1 used as part of a density gage (see D-49345), the maximum activity would be:

of Cs-137:

5/3.2mR/hr

  • 85 mci = 133 mci aof Co-60:

5/1.9mR/hr 3 mci = 7.9 mci a

For simplicity, we request that the SH-F1 be licensed for 120 mci of Cs-137 and 7.5 mci of Co-60.

For any configuration, some of which may not be foreseeable at this time, the maximum activity of Cs-137 will be limited to that j

which results in a field intensity that does not exceed 100 mR/hr at 5 cm nor SmR/hr at 30 cm.

CONTR6L NO.8 6 89 &

o USHRC-5 February-3,- 1989 Ouality control Sealed source:

Examination of vendor source certificate for proper activity and leak test results.

Incoming wipe test before placing source'in inventory.

Wipe test of complete device prior to shipment.

. Wipe test counting equipment can detect less than 0.005 uCi of activity on the wipe.

Radiation field intensity:

Measure radiation field intensity of completed device prior to shipment to assure that values do not exceed SmR/hr at 30 cm from the surface of the device nor 100mR/hr at 5 cm from the surface as defined by ANSI standard N*538.

Look for voids in cast body and streaming from all mating surfaces adjacent to the source.

Mechanical parts and construction:

Visual inspection of all parts before and after assembly.

Visual inspection of all welds.

Operations check of source OFF/ON mechanism.

Visual check for proper location and attachment of all labels.

Instaliation For either Specific or General Licensees, it is. requested that the device be allowed to be placed in position by'nonlicensed personnel such as mill-wrights or installation contractors. :The device will always be placed i6 position on the pipe with~the source holder in:the OFF condition because it is shipped from the factory padlocked in the OFF condition.

Only the licensed.

personnel responsible for the device (for specific licensees) and-Ohmart' service personnel (for general licensees) have the combination to the lock.

A cardboard tag drawing A-25864, will be attached to the combination lock advising the device may be mounted in place only-if the source holder isflocked OFF.

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CONTROL NO 8 6 8 9 9

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,4 USNRC 6

February 3, 1989

- Wipe Test and OFF/ON Mechanism Test Interval A three year wipe test interval is requested for the SH-F1 source holder used as a part of either a level gage, a density gage oc-a weigh scale.

This-request is based or the long succeseful history of other, less rugged Ohmart source holders such as the Model1SR-A, SR-1A, SR-2, SHD, SHLG-1 and SH-100 which are already approved for a_three year _ wipe test inttival and the long leak-free history of-the Ohmart A-2102 and A-2100 sealed sources which have been in use since 1960.

Testing of the OFF/ON mechanism at three year intervals is requested.

In normal operation the source holder is sonetimes changed from ON routinely during maintenance or during the standardization _ routine.

If the OFF/ON mechanism fails, it is serviced on the basis of measurement performance malfunction.

Radiation Safety Instructions Radiation Safety instructions will be included in all manuals supplied with the SH-F series source holders.

When used with a level gage, a weigh scale or a density gage,

- distributed tcr a Specific Licensee, Radiation Safety instructions, RS-105, will'be used.

When used with a density gage, distributed to a General Licensee, our new Radiation Safety instructions, RS-115 willibe used.

A copy of each is included.

Servicina The Ohmart Corporation ers a'. full range-of services to its customers including: s art-up supervision, radiation surveys, leak tests, leak test Kits, OFF/ON operational checks, training i

classes at users plant or at the Ohmart factory, and disaster assistance.

Details of Construction Details of construction and drawings'are considered proprietary-and are included as an attachment to this request for approval.

These details and drawings are transmitted to the NRC in confidence and must be withheld from public inspection.

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February 3, 1989 This information is not available from any public source.

Public disclosure would cause harm to Ohmart's competitive position because it would alve competitors access to the knowledge Ohmart has gained through substantial R & D effort and field trials.

Sincerely,

%1.fr Robert L. Hudson Production frigineering Manager

.s RLH:rd C:

P. Sieck D. Jahns L. hayes G.

Robertson Enclosures and attachments:

Withhold from Public Inspection Attachment, Photographs, check, C-49349, A-3?739, B-33568, A-22425, A-25864, D-49331, D-49350, D-49345, RS-105, RS-115, D-48882, D-48883

< File:

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L ll\\IIIlll c o n.. o n ai o n y

PITHIIOLD FROM PUI)LIC INSPECTION Attachment to Reques: for Approval - SH-F Series Sourco Holder, Model SH-F1 DETAIhS OF CONSTRUCTION The Model SH-F3 is the first version of the new SH-F series source holders that feature a new " fireproof" design.

This design uses only materials that will withstand a temperature test of 800*C for thirty minutes.

This test is a requirement for many licensing agencies in the International market.

.s An outline of the SH-F1 in a density gage configuration is shown in drawing C-49349.

A sectional assembly is shown in drawing D-48882.

Overall dimensions and general material is shown in drawing D-48883.

Radiation profiles are shown on drawing's D-49331, D-49345, and D-49350, for both Cs-137 and Co-60 isotopes.

As shown in D-48882, the source capsule is held in place in i

the holder by a steel retainer backed by a steel slug. The capsule and steel slug are separated by a compression spring.

l This assembly is held in place by a threaded pipe plug.

After the radiation label (A-33739) is attache,d to the end of the cource holder body, it is not obvious how the source capsule is laaded into the source holder.

The body and rotary shutter are solid metal castir gs. The enutter is inserted into the body and held in place b'; a threaded retaining ring.

After assembly, the threads are peened to urevent removal of the shutter.

The operating knob is cast into the end of the shutter and is slightly recessed into tha retaining ring after assembly, to prevent accidental damage.

The knob center is ribbed'to allow rotation by hand or by use of a wrench.

An arrow cast into the knob indicates the "ON" or "OFF" condition of the holder.

All materials contained in this holder will withstand a temperat're test of 800*C for thirty minutes without any_effect on radia; ion shielding or shutter operation.

No lead is used in this design. The materials used may vary from cast iron, steel, or stainless steel, depending on the environmental conditions being subjected to, but all containers

.e subject to a maximum of 5 mR/hr at 12" (30 cm) radiation field criteria.

The data submitted is based on cast steel body and shutter.

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RS 105 (11-87) l RAD _IATION SAFETY FOR SPECIFIC LICENSEES DENSITY, LEVEL, AND BELT HEIGji CAGES i

1.0 INTRODUCTION

Most radioactive material,used in gaging devices is reaulated b7 the U.S. Nuclear Regulatory Commission.

The NRC issued licenses to users and manufacturers of gagine devices utilizina radioactive mater 4als and inspects sites where materials are used to determine compliance with the terns of the license.

]

The NRC has issued rules on:

1) instructions to employees <10 L

CFR, part 19), 2)* the licensing of radioactive materials and devices (10 CFR, part 301 and 3) radiation safety (10 CFR, part t

20).

A brief outline of the regulations is given in part 4.0 of l

[

this section.

During 1962, the NRC began entering into agreements with individual states to transfer regulatory authority to them. _

Known as Agreement States, the:r r*gulations closely parallel those of the USNRC and are e.'

'.ly identical except that the Agreement States usually regt ne use of ALL radiation producing devices.

i As of August, 1987, ti+ Agreemerm..ates were Alabama Kansas North Carolina Arizona Kentucky North Dakota i

Arkansas Louisiana Oregon California

. Maryland Rhode Island L

Colorado Mississippi South Carolina Florida Nebraska Tennessee l

Georgia Nevada Texas L

Idaho New Hampshire

'Itah Illinois New Mexico Hashincton Iowa New York Only those individuals specially licensed to mount, repair, relocate and/or remove the part of the cage containino the radioactive source may de rio.

Each specific licensee should carefully read his particular License to determine the exact conditions of his license.

When a license is issued, the regulatory agency - the NHL or the j

Agreement Statu - sends a copy of the regulations with the license.

Ther,e regulations should be kept with this instruction manual.

RS 105 (11-87)

Page 2 2.0 GENERAL 9

Gamma emitting radioactive materials radiate electromaanette eneray very similar to licht except that it read 11v penetra*es opaque materials and read 41v passes throuch several inches of steel or other dense material.

The ability to penetrate material can be used to advantaae in the measurement of process variables such as density, leve3 and thickness where E change in detected radiation indicates a change in process variable.

Sketches of various cases are shown in Figure 1 at the end of this section.

i Radiated energy is harmful to the human body only when absorbed S

at an excessive rate.. For example, a alowina incandescent lamp cannot be held in the hand _without sevare discomfort or a painfu'. burn resulting.

The hand can bo held close to the lamp for seconds, at c few inches for hours er several feet away continuously.

By use of an insulating iacket around'the lamp or with an insulated glove, the lamp could be held indefinitely without discomfort nr injury.

Radioactive energy atid radiation is analogous to light energy and radiation with the radioactive source taking the place of the incandc<sent lamp.

Permissible human exposure to a radioactivr. source is de7endent upon:

a)

The number of millicurias of radioactive material it, the (similar to the wattage rating of a lampi

[

source b)

Distance from the source.

c)

Amount of absorber between source and body.

d)

Percentage and portion of the body receiving the radiation.

The term "m1111 roentgen per hour", abbreviated mR/hr, is a measure of tha radiation-field intensity in air.

When radiation is absorbed by the body, the term " rem" or " millirem" (0.001 rem abbreviated mrem) is used.

This distinction is necessary because not all radiation.affects the body in the same manner.

For gamma radiation, the millirem in equal to the milliroentaen.

The Nuclear Regulatory Commission 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 iajury is not complete.

Thus, it is wise to receive as little radiation as possible.

To guard against possible over-exposure and to maintain a record of personnel routinely exposed

.o radiation,

1

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RS 105(11 87)

Page 3 the NRC requires personnel monitoring of persons who are apt to receive more than an average of 25 area per week or who are exposed to a radiation field greater than 100 mR/hr. When personnel sonitoring is required, a record must be kept showino the dose received.

When records are kept, and if the employee requests it, the employer must furnish a written report of radiatiori exposure annually and on termination of employment.

j In the majority of OHMART installations, the source is contained in a lead-filled source holder with an OFF and ON position.

The holder is designed so that the radiation field is 5 mR/hr (or lees) at a distance 12 inches from the surface of the holder when it is in the OFF position.

The source holder must be in the OFF condition when it is mounted on the process.

When,the source holder is mounted on the pipe or vessel and turned to the l

ON position, the' pipe walls, the process material and the mounting brackets ^ absorb most of the radiation.

Again, the i

field intensity is about 5 mR/hr at a distance of 12 inches fron the surface of the gage.

Thus, a person would have to be within 12 inches of the gags for 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> per week to receive 100 area.

A perdon would have to be within 12. inches of the gage for 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> per week before he would be required to have a personnel monitoring device, such as a film badge or a dosimeter.

Long experience with hundreds of gages, where the source is contained in a source holder, indicates that the dose received by operators, maintenance personnel and supervisors is less than an average of 25 arem per week.

Thus, for gages where the l

source is contained in a source holder, it is usually not r

I nccessary to provide any personnel with monitors.

Whether ur not monitoring devices are needed should be determined at the gage sita,at the time of installation in the i

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 9 ell.

Installation of the source in the well should be i

L done as rapidly as possible.

All the necessary equipment should' be assembled prior to opening the shipping bon 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 the OHMART Corporation.

When an unshielded source is installed in a vessel or when it is wipe tested, the radiation field is usually i

greater than 100 mR/hr.

Thus, personnel monitoring in the form t

RS 105 (11-87)

Page 4 cf film badges or dosimeters is required.

A record of the film badge or dosimeter reading must be kept on Form NRC-5, a copy of which is attached to this section.

Since records must be kept, the_ employer must furnish to the employee, if he requests it, a record of his 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 of 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 coversets 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.

Some gages utilize radiation that is reflected, or backscattered, from the process material to measure level or density.

For these gages the radiation source and the detector are mounted on the same side of the vessel.

For backscatter gages, the radiation field intensity at the detector is low when the vessel is empty and high when the vessel is full.- Both gamma radiation and neutron radiation are used with backscatter gages.

Conventional survey meters can be used to measure gamma radiation, but a special survey meter is required to measure neutron radiation.

Before the gage is put into operational use, a radiation field intensity survey must be performed and a test for leakage of radioactive-material must be done.

If the gage uses a source holder, the source holder must be checked for proper operation and functioning of the OFF/Ol' indicator.

These procedures can be performed only by a person specifically licensed by the NRC, or an Agreement State, to perform them.

The license issued to the user of the gage may, or may not, allow him to perform these procedures.

The user should read his specific license to determine the exact conditions.

1 I

i RS 105 (11-87)

Page 5 t

3.0 FIELD INTENSITY CALCULATION The best method for determining the radiation field intensity is by measurement with a survey metar.

However, the field intensity can be calculated fairly accurately.

The radiation field intensity can be calculated from (k) (mci) (1000)

D=

ld)2 D = Dose Rate, mR/hr aC1-Mil 11 curie y,alue of source d - Distance to source, inches k - Constant, 1.3 for Radium 226 0.5 for Cesium 137 l

2.0 for Cobalt 60 i

0.016 for Americium 241 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 fnches.

The source is 10 millicuries of Cs-137.

For the above example the dose rate would bei Dose rate. (0,5) (10) (1000) = 12.5 mR/hr (20)2 And the dosage received would bei 10

= 2.1 aren Total dose = 12.5 mR/hr x gg To calculate the radiation field intensity on the outside of the vessel with the source installed in the source-well, a set of transmission curves is needed.

The attached craphs show the percentage transmission of Cs-137 and Co-60 vs material thickness for a variety of materials.

Note that the material thickness scale is different for lead and steel.

Calculate the radiation field intensity at 12 inches from the surface of the vessel shown in drawing C-1142 when it is filled with water.

Total distance = 12 + 12 t 24 inches Dose rate for unshielded sources (0,5) (l') (1000) 0 8.7 mR/hr D=

=

g),

i RS 109 (11-87' Page 6

{

Percent transmission of gamma radiation through.25 inch steel l

(vessel wall) + 0.113 inch Hastelloy (source-well walli + 12 inches of water = 0.90 x 0.96 x 0.335 = 0.2P9.

Resultant field intensity = 8.7 x 0.289 = 2.51 mR/hr.

Note that when the vessel is emptv the field intensity ist l

8.7x 0.90 x 0.96 = 7.52 mR/hr To estimate the dosage received by personnel working in the vicinity of the source, the occupancy must be known.

Suppose l

that a man worked 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> per week within 12 inches of the vessel.

He would receive a dose of 25.1 area /wk with the vessel filled with process material and 75.2 mres/wk when the vessel is empty.

He would then require a monitoring device.

4.0 NRC REGULATIONS Some of the most important aspects of the NRC regulations are given below.

1)

The " Individual User" listed on the " Application for By-product Material License" is responsible for the source.

If 5

this person is transferred or is changed to a position where he no longer is responsible for the source, the license must be amended prior to the assignment of the new " User".

2:

Use of the source is usually licensed for a particular plant site.

If the source is transferred to a different plant i

site the license must be amended prior to the transfer.

3)

A record of the initial radiation ~ survey must be kept for reference.

4)

Records of the periodic leakage test must be maintained.

5)

A label must be attached to the source bcider, 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 the OHMART Corporation prior to shipment.

For sources in source-wells, an NRC approved tag is placed inside of the source shipping and storage container.

This tag should be removed arid attached to the source-well.

6)

The areit in the vicinity cf the source must be posted r

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.

l-l r

.RS 109 (11-871 Pace'7 7)

Personnel monitorino is required when personnel are apt to receive a dose in excess of 25 aren/wk or when they enter a radiation field grtater than 100 mR/hr.

B)

When the source is no lonaer needed, contact the OHMART Corporation to discuss disposal.

The source may only be sent to a person or organization specifically licensed for the purpose.

9)

The regional Operations Office of the NRC or the equivalent State agency must be notified of any incident, such as a fire or explosion, which involves the radioactive material used in the gage.

The OHMART Corporation should also be notified at 513 /272-0131 ( 8: ? ) A.M. - 5:00 P.M. weekdays) or 513/272-0135 (evenings and weekdays).

l 10)

If personne[. Monitoring is required, a record of the radiation exposure must be kept on Form.NRC-5 or equivalent State form and, if the employee requests it, written notification must be given annually or on termination of t

employment.

11)

If a person receives more than 1.25 rea per calendar

+

quarter, he must be notified in writing of the exposure and the

.i NRC must be notified.

l 12)

Any area where an individual, if cont:nuously present, can receive a dose in excess of 2 milliren in any one hour or where he can receive more than 100 millires in any seven l

consecutive days must be treated as a restricted area and access to the area must be under the control of the licensee.

l

- 13)

Employees working in, or frequenting, a restricted area must be advised of the restricted area by posting of Form NRC-3 or the equivalent State form.

The NRC regulations state that this form aust be poLted so that employees can " observe a copy

(

on the way to or from their place of employment" in the restricted area.

Thun, 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, Fora NRC-3 need not be posted.

y I

i 9'M"

9 m

~.

. ~ - - - -.

i i

RS 105 (11-87)

Pace 8 r

i LEAK TESTING l

l 5.0 CENERAL j

i All OHMAr.t sealed sources are of extremely ruqqed constructior i

I and are generally doubly encapsulated in stainless steel and doubly sealed by welding.

All Cesium and Cobalt sources ate so constructed.

Because of this rugged construction, the possibility of radioactive material leaking from the source capsule is very remote.

Usually the source capsule is enclosed in a source holder to provide shielding for the radiation and to permit an ON and 0FF position.

Thus if the source capsule should leak, the possibility of the radioactive material starating to the outside of the source holder is extremely remote.

1 In addition to the above precautions and rugged construction, the sealed source is leak tested during a 30 day period prior to shipment.

Sources showing the slightest evidence of radioactive material on the external surface of the source capsule are discarded or repaired.

However, since industrial use of sealed sources dates primarily from the general availability of radioactive isotopes for industrial gaging use after about 1947, the Nuclear Regulatory Commission requires that sources be tested for leakage at specified intervals.. Only Kr-85 and Tritium sources are exempt from leak testing because they are gases.

Certain sources of very small' activity are exempt from any testing.

The leak i

testing procedure detailed in these instructions applies only to the OHMART Model LT leak testing kit supplied with the OHMART

" Leak Testing Service."

This service may be purchased from the OHMART Corporation on a five (5) year contract basis when the wipe tests must be performed every six (6) sonths.

OL it can be purchased on a one time basis, in-the case of three (3) year wipe test intervals.

The service must be purchased for each individual source.

If this service is purchased the OHMART Corporation wills Send leak test materials at required intervals; analyze the leak test materials for the presence of radioactive materials issue a report on the results of the leak test.

5.1 SEALED SOURCES IN OHMART SOURCE HOLDERS The source holder must not be disassembled to test the source capsule.

Testing of the external surface of the source holder is adequate.

.1 Take the plastic bag containing the swabstick to the source holder to be tested.

Open the bag and grasp the l

swabstick by the end opposite the fiber tip.

l RS 105 (Al-87)

Page 9 i

.2 Hipe the external surface of the source holder with the 1

fiber tipped end.

Hipe all seams and around rotor shafts.

]

These areas are most likely to be contaminated if the source leaks.

Do not touch the fiber tipped end or allow it to touch other objects as this would spread contamination if the source leaks.

.3 After making the wipe test, replace the swabstick, fiber i

tipped end first, in the plastic bag.

Zip the bag closed securely.

.4 If a blank form has been provided, fill it in.

Put the j

filled-in form, if any, and the bag (with the sumbstick in it) inside a sturdy envelope or other suitable mailing container.

Attach the Ohmart address label (supplied with the kit) and mail to the OHMART Corporation, 4241 Allendorf Drive, Cincinnati, Ohio 45209.

[

l

.5 Upon receipt of the wipe, the OHMART Corporation.wil'1 1

perform a very sensitive test to determine the presence of radioactive materikl.

If the wipe is free from contamination a notice will be sent, via mail, that the source is leak-free.

If the wipe has a significant amount of radioactive material, an emergency notific.stion will be sent, via telegram or telephone, advising that the source holder must be taken out of service and I

returned for repair.

The emeraency notification will contain detailed instructions for removal and shipment of the source holder.

5.2 Ef>&n SOURCES IN SOURCE-HELLS The testing of sources in source-wells is potentially more l

hasardous than the testing of sources in source holders because of the absence of the lead shielding provided by the source holder.

The person performing the leak test must be thoroughly faciliar with the procedure in order to keep the radiation dose to the lowest possible level.

The dose received is dependent on i

(1) the total timp that the person is exposed to the source and l

(2) the distance between the person and the source.

In e dur to minimize the exposure time, a pre-planned procedure shoulo be l

used.

In order to maximize the distance, the use of a banclina I

device either for the source or swabstick is recommenacc.

Tne distance can be maximized further by working with the arms fully extended from the trunk of the body.

Most source capsules are installed in source-wells with a handling rod which can be used as the handling device when performing the leak test.

When a handling rod is not used with the source, a pair of long tongs or pliers can be used either to handle the source or the swabstick.

The tongs or pliers must not be used for any other purpose and they must be stored, when not in use, in a container separate from other tools.

9 s

RS 105 (11-87)

Page 10 To further reduce the radiation dose, various techniques can be devised to suit a particular situation.

For example, the wooden end of the swabstick can be fastened in a vise and the source capsule wiped on the fiber tipped end.

A trial wipe, using a " dummy" source capsule, is recommended to determine the best procedure.

The " dummy" source capsule can be made of common steel or brass bar stock to the same dimensions as the active source capsule.

The use of a radiation survey meter, to monitor the working area, is highly recommended.

The source empsule must not, under any circumstances, be handled with the bare hands.

Even in an eneroenev, the source capsule must be handled with tools rather than the bare hands.

.1 Take the plastic bag containing the swabstick to the arek where the source will be tested.

Open the bag and grasp the swabstick by the end opposite the fiber tip.

.2 Nipe the source capsule with the fiber tipped end of the swabstick, Pay particular attention to the end of the sourew capsule at the welded joint as this is the area where leakage is most likely to occur.

Do not touch the fiber tipped end or allow it to touch other objects as this would spread contamination if the source leaked.

.3 After making the wipe test, replace the swabstick, fiber tipped and first, in the plastic bag.

Zip the bag closed securely.

.4 If a blank form has been provided, fill it in.

Put the filled-in form, if any, and the bag (with the swabstick in it.'

inside a sturdy envelope or other suitable mailing container.

Attach the OHMART address label (supplied with the kit) and mail to the OHMART Corporation, 4241 Allendorf Drive: Cincinnati, Ohio 45209.

.5 Upon the receipt of the wipe, the OHMART Corporation wi11 perform a very sensitive test to determine the presence of radioactive material.

If the wipe is free of contamination a notice will be sent, via mail, that the source is leak-free.

If the wipe has a significant amount of radioactive material, an emergency notification will be sent, via telegram or telephone, advising that the source must be taken out of service and E

returned for repair.

The emergency notification will contain l

detailed instructions for removal and shipment of the source.

1 k

RS 105 (1088)

Page 11 9

l PART 20 a STANDARDS FOR PROTECTION AGAINST RADIATION l

APPENDIX D.-UNITED STATES NUCLEAR REGULATORY COMMISSION REG ONAL OFFICES 4

f2Y' Addr osase Regon t Corrm*ut Osteenre t>sinct et Cokartaa. haasna, USNRC,4T5 Anertiale tems ang of (2151337 5000 Wawrut Massamusetta, New Hamgenre. New Jersey, New Frussa. PA 19406 (FTSI e44-1000 t

YoA Pennseverua. Atodo leend, and verrrant.

$. Royon it; Alatama. F kruna Ger.rgia, Kentxry, m uavra. Nortn USNRC, 101 Wanone St,eet RW, (404) 2 3 4503 Carohna. Puerio Rco, South Caronna, Tennessoa. Vrgrrha.

Surte 3100, Anama, GA 30323.

(FTS) 242-4503 Vripn leaaruss, and West Vegreau.9 Repon tet. Ihr on, Lneana luwa, Watsgan, Wennesote. WW USNRC, 7M Roosven Road, Glen (312) 794-5500 g

Elyn, IL 60137.

(FTS) 388-5500 Orso. and Wseemnean Repon N: kaansas. Colored.. lonno, Kansaa, t rmana. Won-USNRC,611 Ryan PLars Onve, Sune (817) 600-4100 g

tana Natraana, New Meuco. North DaAbta. OkWoma, Sowin 1000, Arengton, Tx 76011.

(FTS) 72th-4100 m

Da60s. Tessa, Laan, at's Wyortung

_A USNRC, Repan IV Urarnum Recwory (303)236 2805 Repon N; Fwed Ottee V

~

Fund Offee, 730 Samme Sweet, (FTS) 776 280$

P.O Bou 25325. Denver, CO 60225.

Regon V: Alaska, Arnona. Comm, Heena, Nessa. Crepn, USNPC.1450 Mene Lane, C,ns 210, (415) 943-3700 Wawwt Creet CA 645tA (FTS) 463-3700 Poczfe Trust Terreanos, arse waerepan

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i,.w.n e a.a tDE NT 68 C ATION 1 NAWE (PRINT. lam, fern og meg @ eel 2 $0ClAL $4CURITY No.

3 Daft ;F BIRTM fatoam.dev, veert

4. NAME OF LtC&N&tt t
6. 00$t RtCORDED 804 Sesedy: Whom te*V.

6 WHOLE BODY 00sg

7. WLTM00 0F woNiTORING tag. Em tio,-

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STATVS tremi PS:Peeket Cw - PC. C4 cwiete. Cois i 9BPt dPts ontIGa i X OR GAesWA stTA NEUTRONS 8 PERIOD 08 ExP06vRt Dost POR THE PtR:00 tremi 13 RUNNING vot AL 70m (F rom.101 CALENDAR QvamTER

9. X OR GAMM A
10. 0ET A t t. Det yTRON
12. TOT AL t'em' (I ;( IIME ACCUMULAll D DOSE ts 804Tema t014 esuunt to 99 tat ame ttekt te to?4 ACCNTRO 19 Plant act past ten te sene et unautt e pas 108 M essmen t EnD66 WEEG l'ennt acCtanAaf80CM 4 Won' mu

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intSTRUCTIONS FOR PREPARATlON OF FORad 8eRC 5 e v p,. e.t.,.,e,,,,

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,er pesq C.4 i The total arewpatecessi eadiet.on come i

ifweerms e a t Uer eens,*eent as.esrtur havene a es so eseeuo d t,y tw me..mai men tm of re.s.m.w -m iceiwo e,oow e.eniced ses=e cm The en to to esan of ictemos of m,w whee inoey, et v' ems. or tort one asuoi ng any occurabone ewee trom nowrces rw Comm iwon H t%e e

ehmied to re armo en esperate forma.,naeus to esse to me= eves e to sources of reo espoon.nica owemo sn, stion noi those pets of the tun has teen erkded a whose amey on e form meentsense for recare.oene to the Comm enaar nuene, sa,isr campes. >g 8 s>rm At C4 or N AC 4 ene possunrwi nnsee try ng whose body e

esponers.

monstwmg esseawnt om not worn liv ene enamove.

town 6 to recer6 whose bocy esps.d only asegen wie pues es veel Thes etevi need tie tenp6ege et e,in,te to entemed that the endeviewet receivec a cose sren med me lessnest a pf 11/4 rums owong each auch cetericer ovariee empoeng the wisarmheel umger the prevemens of rererseh Igen 16.

Enter pw sets: ceienco< overter came tryn tiem 13 (or i

l 30101(b) suh.cn essaios up to 3 r, ems per euerter se Die trem stem 12 d cuaterly coers art eate*ed on 8 tem ail suhoes hody, inser en fins esem t e unissed part of ger.

and wie ese ses yistmg the end of the caserer overter l

mnetse ecasmussteg$ of t,saken treen iprovious reJortei of LWR 1{

een en wouch sne Gow was regewed te e. Mar.:n 30. ;962) esposure. e e.. igen i g precocmg 5 erm Alv6 or Aest lira le rid.sitern 1e **:G enter Imat com.

+

er toen 13 of Itsn Ir, Otton tes Pe'E 80ye Acewmulatec Come

, tne hat m.te evoivaies et m no e reesim eensw misc.ew,..in e uceave erw os a i L ever..a. e. =t.se...eu , e.. re .ee m se n,.ac.e.no ywuco e. en t e.es w..n. -oo ac., im...se et.. == eat ice tem e. we esme.acs caeas svari e aseen we eneag hreaen the enceii,= cou p ew es swe u se4.e a.i4.e e to es. esea s teve wedest 3 a0Utiti Ust5 tne esermei a me, w sus n ero=en esta se owie f eestw and Saw sp=en== emes a maamwet re se.e.si.g secei. e.eewi esco o be me.e.e.en e=eseved a ree.ene uwten en a comea at er namWFy beel yte espearre entsvee by mpwee M.trl ihe esdrmas on mag og br oncewe to en emues= see f eenes.Siem, e nece arme e sw **at tas edw=emea ind.ceien e emehan se sewme> ceuisa et i.= eas e sae tev e e e. e ee asinenw e pre.te'erseeeet 4 4 wwttMt a Disclosualis maarDatoav De votuut Any A=01FFICt De sepiviouAt es not PaovioinG msoevatices n a eow,aine twai ves ter=vi m me.nied ratorme.en aciveas nec ei etera, eveba. me em, m awnee mai ceanew Iwe h at i en esta eaa4 e is. eas* c-maart mesmeat e eeweet enea te Cl a M M2 ise re to se e ae. m,6ect tw e ven to esecemeat ectea a ecersec..s* 10 C t e M 60 t r tae sace' occa,. wr e sere se ein.no teen haC hei sa ecwsw meanter nei m tent u tw temcionace e omaa asari s 6.rwisvet r* sat r** ire esme= et es was en e e== esia a me.ais me m l SY$tt# MA44$t 8 51 an0 A00atts 0.ruto. Once W measse= eat saler wom ew P,arem Coane. U S tec., nep.e,. Cea..nea nuhacea 0 C liti% INSTRUCTIONS FOR PREPARATION OF FORM NRC 5 thee,e erion ese w ee oesang o' the tonn er e ewe ene invites rey.e e seet e,pi,ietari the ves.,ei o e to e,,.,,a en,,m e resere c y,ov.n.e., en te me te wmet.on ooverse on thee form a re 80 yta As nmerFTeat ye to te eaWprewc sa togg typ trwpoa portant to Sect pa 70 a01 of 'Sonaeros for Proteet+wi it novi nen ene sa attormente e. or epa ?0 4 6c w>er,ce ano,in.a.ons ye man to o,,e,,,,,,,e cou e.e,n.,.te-e Asemet Aeo.eten " 10 C8 A 20 a e averent escas of occupetsonal secca cop oe es ernes reo eison empcuo'es beh a recae must to moentered m.cei cacnsiet u a to te me.nterwe en cwi e t mater e aan eri los et we vee e spec,o, iv r,,ae ter sec+ enomousi 's seuwa personnes mew =teme es rouwwed t*ws eerire en eng cow

  • e e t, in ie t aw uney Sect oa 70 202 hole that a soprose F wm N AC 6 e to to v

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ti se en o' =+=c*e 01 hens aws tworms a 441 teet erio 6e,s o e ewnwrecer voive r

eneles a swo emo Ov item 6 teso= 'emm 12 Aod the vegen unoc seems 9 to y.c i

  • e, ew% pe,.oe (vl espeshJee,ortC retor6 the totsi LssteJ tuskoe tiv eterum We enstructetra ered to6teenef entorehoitori sa tencv6eting the
    • f eter" as en tet see thea 10v may te o.sregema ehreetty periment to compeeting the term I

II I e rW'Wteng tot & ate *iPC oa the togst et seemes m oriers '% to tur me'20 363i t4l oeteres c.siersaw W W9ea W P orey ash Han t beif +nsdeisterv maarter. 8vo entrv nees te meae en te. nem et me, eten 2 teHeaparistor, encept that, et pictweess he no scool essense mueror reo.etion ooere ye,eco,o,s.e soms e ee numter, so were " tere" e oi be weerted

40. Il one 12.

v $f M','se% U8etsee Asemmedoed Doe fWhate Destl ee,,,,, e _ imi.:,..e ieseruse. s,o., to.c,oe,ie er,0.v,~es, neige meteen tico en pe eyeoh 20,101isi imms a m item & **Dese to 9e estete beoy* thef t in seemed te enc 9ede any %4 9weise le neett not en twapleted Momeve in meigae sees to en whose tmov. peneen. acteve biaseformeng pie ietw weisse boov pow e each seienne e, ore, rotoroeo ergris, heed and trunk, or twit of eye Untre the teneet et Igym 13 ier item 12 ef $ grterly ooert are emeeed en hem of tre evet are protectee with eye ahwess ooes retorceed 121 sheets net en como 1 ise em a whee boe, aos shouse.etwee en one meweroa H wi outvetkel e esp *eed unoer i e.i ~ en ns o' Peregra,ph 70 toi p<ov se Lrcae e tNo.,oo.ww,es,e,er, etnortoe hev.m,g a tN.etnes,s o.f nt

  • eenpie= i-i mrowe t ew ca.9 ose enyc s

true ore. o te o o ore r EuFW yed isoien he eget og toiser Veiweg en iteen 1) when en the TEE ted art

  • e thees herestg a greue omsseretent bec%neet of et toast mg/cm. goes recorded as weto6e sooy set fnsinde ed a telence 'twerie' ".w weewei 'a let* 10 *wst to D*tse'

'er**] to 'eee speet for ee-h me=sowa shouse enceuce the caer misverso roup a jamue ogweveient %1 Saw Ife ermows total accumw6sted peer try* pre eteorber hoverig a pucknee of 1, mpAcm er tog. eam a som receros to t>e snow.owei se f f cem At C4 trom item 16 ofTarm At C & e NRC 6 m hem 11 o Does recorood ei com to the then of the whose boey, hones ano soreenas. or teet one eatles thouse meauce tre som erNhC4 the tote, arcuosteans' eed.etion ooie tenetwared thrgwP e t8thee espssee6ent etseerteer hoverig 4 reassved by F,ie ertowsmai mwet tie eftlered en th.t etern thickrues of i mycm or tres The eene te vie sun of enewome,es noi tee,Stional oow escenee hem tou ces on accuo r the whose toov. nacids and toreams or teet ene askeen et re,a,et year sowei weg espova,e,cm,,e Commen oa we by th le the shtmsto te recorme on iaparete terms unesse the eene to e ces n,ed stion not those parts of me tmov has toen vekstood a does to the tuonero by the Commis.on oure a n nw wenaer owerte, whose tioo, on e term meenterned for recardent whose body erger Cornpoetmg F orm At C4 or C 4 and pergarmes monst,oring es,ipment ma no: worn b, the me.veowe. es ponsre etum 6 TNs aten need to semp6eted erov when es sheet es weed et osen id te esasmoo thei t'e indeviousi recewoo e coer to recara w++ose buoy empoesten ario be 'mennee a c4 i t/4 rums oveing each auch ceiencer ausew espoone the moevuwei unoer t's pes =resorn ei Pereyeph tiern 16 Enter we totai ca.encer overw some teen item 13 tot whose emov t aw, own wo to 3 reme pee overe to the eram etem tf d awaseriv sows ce entereo en tie

  • 12i 20101tbl wh ch en m via even t'e ursseed part of per and too new mi.yetmg pe ene n' the wence neerie.

meerve occumwisied oces taken from previous recore of m whe the oow was rece=ec 4 6 Merces 30 ils62) estamure. e e, aten 18 of tre F Al G 6 or ison 16 And item to aid isem I6 ano er er that wm peAG6 or item 13 of f arm A C 4 er i R

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  • 17 Ihe u wesc part of the P AD n

Sie laceriese meentemt a current record of Wie oogst retS8ved N het partiers of the (detsme Accu sw6sted Dcate ter a tsy the mclivedsel eAd here not a vet been entered on the IPe snoivihet remo.nmg et the eno of tre period form. The potted of etpoeJfe shound giacety F5e dev he SovWed by thel Oeet measurernent of het esposury we snatneted trid tDe dev en wheon 11 era termmated P or earnp6e of onDv eue"te'tv gment ge enterpa, theyreOd of empreure Oor me forgt gesenaer egwertoe of isu #ngit tue tphen en tynneng from Maricev, Jaiwery 1,1962 thrense Fricev, Meren 30 t $Q and wou4d te moscated en Ones sten a Jers 1.1962'4 der.uw. 1962 It numekly ogna era enterect e hWn booge eesued Mondey mornerg Jerwerv 1,1962, ered peeked $ recoy Jamaerv l. 4962, wav d te snoscoted as Jan.1,1 Jan. I e 1962 esivaCY ACT TTattnettri Peri.seni to % V 3 C %%2sel 0) erected ate aan be etnoe 1 o' the P'erses Att el 11N iPeesec Lee 1)lPll res toessiaq oeemeni et tus mees to *e. ewe's one se.se. ea sa een norme neg= eve e C maawea en F ere h RC 6 in's =4=esea is se.n e4 e e mw= et eme as ses.ene+ e si n e C 7 7 eae om, we e' 40 leseesi hegene 4%)se 40ctobe' t il PSI I avin0 Aif f Set.eas t) 63 45 II 103 toa 16160 eae 16 t le) ol the atomic t apre Aci a' 19i e m eawae.e is t u 5 ( 7C )) 73) 70% 7 ' $ i ?'33 s 71H 170llet one 2 79 tieH f ew eesteree, te es.erieme the oc.si uccies aw*eer e 10 Cf A Pei 70 i an 'a' * ** e* e ***e ** "* h R C 'a.** *=e. i.n. s vs e.e ei ree.ei e e s e i s. essocmes.e 'a o. oceaes er., i. e ae - e ) et shC PP & t PVIIPOSI St esortet+at ei teivleit retPedesemidt to 8heaster sad tegmose t'W selett e C hee.e4 prgriggeg et seg eg enpeg Itas esse sesemieg a mes*"S v t e* es' sc a e' be 8* tv a i eeni one song ee n neews eenevente amoat evrei e' hcoaeres one e=ent liceawet a=the eart t.see Dete ** ee# es eise is es ence i e.e.et * 'a. o..aoa t ou8 deseest 3 90W fiti U$t5 t he **er*ma aev be esse se premse este se ome f eeeees saa Stos eer.coi weretres e mewierest ead > nei.suas 'so.enta necio's rece es 6. me.e.e.en eneis,os en roe.st.ea weten sa e pe**eapai y manorte, teen one eseeee, eeece 6, mwme ee es.'wi T*w.a'r*e' e me.av tw outeste to en yarwoemiete iespes $ tem o 6ecs serac e

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D 4 wIh e

\\ s ~ n. Y Cw A v p / e e w d> gd A $ Rt %k~ P UR 1{ C H A T Co S Ot L R$ 105 (11-37) "N TIGURE 1 xitcion ,J i ] h ,L.E: 7 L ~ f r-v + saatt./ Krtctoe g sostt Dv Belt Weigh Scale Strip Source 6 Strip Detector Density Gage sostt Kitc m s0URCE = = = = = = = = - HGH ALARM 4 i W m \\ Ettc u ~* ~ L I LOW ALARM Belt Weigh Scale Point Source & Strip Detector Level Gage Point Source 6 Point De :ector I RS 105 (11-87) Page 17 souRtn \\\\ \\ g, g- %g g \\ \\ N s, p. s N \\ w itti m ',s 'N s s s," Level Gage Point Source 6 Strip Detector Level Gage Multiple Point Source 6 Strip Detector r t r, 7 _7: i i ~ a I ' $0VRC15 - fq p- // / / Mit(f0R$ sowr.t / - xitttu /, v' Level Gage Level Gage Strip Source 6 Strip Detector Strip Sources in Source Wells f, Strip Detectors RS 105 (11-87) Page 18 i FADI ATIO : FENETTATION 4 b PM IATIO!; u l }d A /AN \\ BACKS:ATitt ,= MMWh%W%%N** %,7;; ;. watt ' 'i/ ' ' 't/ '/ / .ysu g31:n / y e -e- . x.: y TOP view W '.W. W C 3 e NW \\ DETECTOR SOURCI Level or Density Backscatter Gage Point Source & Strip Detector l l .n ) 1 c. 1 Section P.S-lit ;;i-89 ) RADIATION SAFETY INSTRUCTIONS { R Ohmart DensART Series Density Game with Model SH-F Series Source Epj_ der for Gaaes Distributed to General Licensees.,. i 1.0 GAGE CONFIGURATION tie Ohmart Density Gage measures the density of a process n.aterial flowing in'a pipe by passing a beam of gamma radiation through the material. The gamma radiation is partially absorbed I by the process material and the part which is not absorbed is measured by the Ohmart radiation detector. This arrangement is shown in simplified form in the drawing (. i-j below. i l SOURCE HOLDER DETECTOR HOUSING SHUTTER HANDLE - WEARMEMENT -SEALED ranAL to om asemnacs RADIOACTIVE ~~ GAMMA SOURCE < M9___ __ _.. "_ _-[ 1 = 9 . __.I / Y l LJ_r'_~_l.._.~~E DETECTOR / RER COLLIMATOR RADIATION BEAM . ?. RS-115 (0289) i Page 2 The gamma radiation is obtained from radioactive material which is doubly encased in a stainless steel source capsule. The capsule is mounted in a source holder which is constructed of a cast metal body with a cast metal shutter /collimator assembly. The shutter /collimator assembly provides radiation shielding and a collimator so that the radiation beam is directed through the process material toward the detector. The cast metal body reduces the radiation field intensity to a safe value on the back and sides of the source holder. The source holder has a cast metal block, or shutter, which can be rotated into position so that the collimated beam directed toward the detector can be turned OFF. The shutter is controlled by a flush-mounted,',srecessed ha.ndle on the top-side of the source holder. There is one'other position of this handle - ON. The shutter can be locked in the OFF position but is held in place by a spring-loaded ball into a detent in the ON position. 2.0 U.S. NUCLEAR REGULATORY COMMISSION REGULATIONS The use of this density gage is controlled by the regulations of the U.S. Nuclear Regulatory Commission (USNRC) or the equivalent-agency of a State. The applicable sections of the USNRC regulations are numbered 10CFR 31.5; 10CFR 30.34 and 30.51 through 30.63; 10CFR 20.402, 20.403, Appendix D. A copy of these regulations is included at the end of this section of the manual. This copy of the regulations are those that were in effect at the f time of writing this material (approximately February 1989). It is the responsibility of the user of the gage to be aware of changes in the regulations. However, the Ohmart Corporation maintains a current file of a11' regulations and can advise the user if questions arise. 1 2.1 EXPLANATION OF GENERAL LICENSE 1 Part 31.5 of the Code of Federal Regulation (10CFR) states that a General License is issued to users of certain gages that are approved by the USNRC. l The Ohmart Corporation has a Specific License to distribute approved gages to General Licensees. The user of the gage, the General Licensee, must abide by the conditions of the General License. These conditions are shown on a metal label attached to the gage and are explained, in detail, in the following paragraphs of this section of this Instruction Manual. l l j! RS-115 (2-89) Page 3 j I 3.0 BADIATION SAFETY LABEL FOR GENERAL LICENSEES In order to comply with the USNRC regulations, a metal label has j been attached to the gage whien states the responsibilities of the General Licensee. A copy of the label is shown on page 8 of this section of this Instruction Manual. I In the following paragraphs, the actual wording of the label is shown in CAPITAL letters. An explanation of the wording is shown in normal type. j 3.1 RECEIPT, POSSESSION, USE AND TRANSFER OF THIS DEVICE ARE SUBJECT TO A GENERAL LICENSE OR EQUIVALENT AND REGULATIONS OF THIS U.S. NRC OR AN AGREEMENT STATE. ) This refers to the USNRC regulations in 10CFR 31.5 i 1 3.2 ABANDONMENT OR DISPOSAL PROHIBITED UNLESS 1 TRANSFERRED TO PERSONS SPECIFICALLY LICENSED BY THE NRC OR AN AGREEMENT STATE. 1 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 can only be-removed by a person or company specifically licensed by the USNRC or an Agreement State and it must be shipped to a person or company specifically licensed by the USNRC or an Agreement State to receive the gage.

3.3 OPERATIOI

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 shutter mechanism, turn the shutter to the OFF position (if possible).

Note that the flush-mounted, recessed handle is designed to-accept considerable leverage from a large wrench.

Telephone the Field Service Manager at The Ohmart Corporation -- (513) 272-0131 (8:15 - 5:00 weekdays) or (513) 272-0135 (nights and weekends).

.3.4 ANY PERSON MAY MOUNT THIS DEVICE IN PLACE INITIALLY, PROVIDED.THE ON-OFF HI'CHANISM IS_ LOCKED IN THE OFF POSITION.

ALL OTHER DEVICE INSTAL-l

'LATION, DISMANTLING, RELOCATION, REPAIR AND L

INITIAL TESTING INVOLVING THE RADIOACTIVE MATERIAL, ITS SHIELDING AND CONTAINMENT SHALL BE PERFORMED BY PERSONS SPECIFICALLY LICENSED BY THE NRC OR AN AGREEMENT STATE.

I CONTROL N0.8 6 8 9 9

J RS-115 (2-89)

Page 4 l

Care must be exercised when uncrating the gage.

If the crate is damaged in such a manner that the gage might be damaged, The Ohmart Corporation should be contacted for advice.

If the lock i

is missing, broken, or not locked, do not uncrate or mount the gage in position.

Call The Ohmart Corporation for advice.

Anyone may mount the gage in position on the process pipe, do the electrical wiring, and turn the electrical power switch ON--if the source holder shutter is locked in the OFF position.

When mounting the gage in position, take the necessary precautions to assure that the source holder is not dropped or damaged.

Refer to the outline drawing of the gage in the measuring assembly

?

manual or installation manual before mounting tha c.m. in position.

a

,e t"'eement Only a person specifically licensed by the t' f&

State is allowed to remove the gage from its ">4ya

  • u dismantle the page.

After these preliminary services are performed, o

specifically licensed by the NRC or an Agreement State must do the start-up of the gage.

This involves:

unlocking the shutter and turning it ON; testing for proper operation of the shutter and the shutter position indicator; making the initial radiation field intensity survey; doing 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 / year.

The gage is shipped from the Ohmart factory with the source holder shutter locked OFF with a padlock.

Lock combinations or keys are not shipped with the gage and will be given only to the specifically licensed person performing the start-up and placing the gage in service.

Usually, this person is the service representative from the Ohmart Field Service Department.

A copy of the tag attached to the lock is shown below.

THIS DEVICE MAY BE MOUNTED IN PLACE INITIALLY BY ANY PERSON PROVIDED THE SHUTTER REMAINS LOCKED IN THE OFF POSITION.

ONLY A SPECIFICALLY LICENSED PERSON MAY PLACE THE DEVICE IN SERVICE BY INITIALLY OPENING THE SHUTTER AND MAKING THE REQUIRED LEAK TEST, TESTING FOR PROPER OPERATION OF THE ON-OFF MECitANISM AND INDICATOR AND MAKING THE RADIATION SURVEY.

o RS-115 (2-89)

Page 5 3.5 DEVICE SHALL BE TESTED FOR RADIOACTIVE LEAKAGE AND PROPER FUNCTIONING OF ON-OFF MECHANISM AND INDICATOR AT INSTALLATION AND AT SOURCE REPLACE-MENT BY PERSONS SPECIFICALLY LICENSED BY THE NRC OR AN AGREEMENT STATE.

THEREAFTER, TESTING SHALL BE DONE AT NO LONGER THAN 3 YEAR INTERVALS, USING PROCEDURES STATED IN THE INSTRUCTION MANUAL.

3.5.1 ON-OFF Mechanism After initial testing of the shetter and shutter indicator by a specifically licensed person at the time of start-up, testing at three year intervals can be done by the General Licensee.

To test the ON-OFF 4echanism, rotate the shutter handle back and forth several times'between the OFF and ON position.

.The shutter handle should move easily but not freely.

There will be some resistance to movement due to bearing friction and the inertia o; the shutter /collimator assembly.

It.is OK to force the shutter handle with a wrench or lever because the handle and shutter are one cast assembly.

If a portable radiation survey meter is available, the radiation field intensity can be measured at the back of the detector housing.

With the shutter handle in the OFF position, the field intensity should be very low.

When the handle is turned to the ON position, the field intensity should increase.

Another method is to use the gage electronics as an indicator.

With the gage electronics turned ON and operating properly, turn the shutter to the OFF position.

The gage reading on the digital display, indicating meter or tecorder should be near or above 1004 of full scale.

This high value reading is a result of the shutter /collimator block being inserted into the radiation beam -

which is the equivalent of no process material.

If the gage does not indicate a difference between source ON and OFF, the gage must be serviced by a specifically licensed person.

3.5.2 ON-OFF Indicator Testing of the OH-OFF indicator means that the shutter indicator must indicate ON and OFF properly.

This can be observed when testing the shutter as desc"ibed above.

l 3.5.3 Radioactive Material Leakage Test I

l This test it<volves wiping the external surfaces of the source l

holder with the fiber tipped end of a swabstick and then analyzing the fiber end for the presence of radioactive material.

l CONTROL NO 8 6 8 9 8

e RS-115 (2-89)

Page 6 The General Licensee may perform the wiping procedure but only a specifically licensed by the USNRC or an person, or company, State may do the analysis for radioactive material.

Agreement The Ohmart Corporation, and other companies, supply a Leak Test The Kit to make this test for radioactive material leakage.

To ust the Ohmart Corporation supplies a swabstick in a bag.

Ohmart Leak Test Kit, follow this procedure.

1)

Take the plastic bag containing the swabstick to the source holder to be testtd.

Open the bag and grasp the swabstick by the end spposite the fiber tip.

2)

Wipe the ext'ernal surface of the source holder with the fiter tipped end.

Wipe around the recessed shutter around the flange facing the pipe and around the

handle, edges of the radiation label as shown in the sketch These areas are most likely to be contaminated below.

if the source leaks.

Do not touch the fiber tipped end or allow it to touch other objects as this would spread contamination if the source leaks.

RECESSED HANDLE RADIATION -

LABEL FLANGE N p

% N

-n A

X i

o I

l lemma 1

4 i

(

Y

}

s - LJ USER'S PIPE WIPE TEST POINTS:

RE0ESSED SHUTTER HANDLE, FLANGE AND AROUND EDGES OF RADIATION LABEL o.,

-my

'g T '.

v,. a k-RS-ll5 (2-89)

Page 7

\\

e 3)-

After making the wipe test, replace the swabstick, fiber b

tipped end first, in the plastic bag.-

Zip the bag closed securely, 4)

If a blank form has been provided, fill in the c

information requested.

Put'the filled-in form and the bag (with.the swabstick in it) inside a sturdy envelope or other suitable ~ mailing container.

Attach-the' address label (supplied with the kit) reading "THE OHMART CORPORATION, 4241 Allendorf Drive, Cincinnati, Ohio 45209."

5)

Upon receipt of the wipe, The Ohmart Corporation wil1 perform a very sensitive test to-determine the presence of radic'at t1ve material.

If the vipe is free from contamination a. notice will be sent, via-mail, that the source is lesk-free.

If the wipe has a significant amount of radx7 active material, an emergency notifi-cation will be sent, via telegram or telephone, advising' that the-source holder must be taken outiof service end" returned for-repair.

Arrangements must be made with The Ohmart Corporation, or other specifically licensed person, to take theJgage out of service.

3.6 LOSS, THEFT OR TRANSFER-OF THIS= DEVICE-AND FAILURE' CF-OR DAMAGE TO THE SHIELDING, OR.rHE SOURCE CONTAINMENT, HUST BE REPORTED TO THE NkC OR AN

~ AGREEMENT' STATE.

j In addition to notifying the USNRC ornthe Agreement State agency,

~

The Ohmart Corporation should-also be notified so that ptoper help can be provided.

If the gage is involved in c fire or explosion, the-area around z

i the gage should be barricaded or roped off until the situation can be evaluated by a.speelfically licensed perron.

Telephone The Ohmart Corporation for help

'he number is (513) 272-0131 (8:15 - 5:00 weekdays) or (513) 2,

^135-(nights and weekends).

3.7' THIS LABEL SHALL BE MAINTAINED ON THIS DEVICE IN j

a.

A LEGIBLE CONDITION.

REMOVAL OF THIS LABEL IS PROHIBITED.

The label may not be removed from the gage and it must be kept clean and legible.

IV

e e-I-

RS-115 (2-89) jn Page 8 L_abel attached to cace for distribution r

to General Licensees r

N1, FOR A DETAILED EXPLANATION OF THIS LABEL,-READ

+

?;

OHMART INSTRUCTION MANUAL, h

SECTION RS -

RECEIPT, POSSESSICd,_USE AND TRANSFER OF THIS DEVICE-ARE SUBJECT TO A GENERAL LICENSE OR EQUIVALENT AND' l

i REGULATIONS lOF'YHIS U.S.

NRC OR AN AGREEMENT STATE.

ABANDONMENT ~OR DISPOSAL PROHIBITED UNLESS 1

l-TRANSFERRED TO PERSONS SPECIFICALLY-LICENSED BY THE h

NRC10R JW AGREEMENT STATE.

4 OPERATION PROHIBITED IF THERE.IS INDICATION OF, L

FAILURE OF OR DAMAGE TO SHIELDING, OR SOURCE' L

CONTAINMENT.

ANY PERSON MAY MOUNT THIS DEVICE IN PLACE INITIALLY, l

PROVIDED THE ON-OFF MECHANISM IS LOCKED IN THE OFF POSITION.

ALD OTHER DEVICE-INSTALLATION, DISMANTLING, RELOCATION,-RCPAIR'AND~ TESTING INVOLVING THE RAD!' ACTIVE MATERI AL, ITS SHIELDING AND CONTAINMENT SHALL 31 PERFORMED BY PERSONS

,t U

SPECIFICALLY LICENSED BY THE NRC OR AN AGREEMENY STATE.

DEVICE SHALL BE TESTED FOR RADIOACTIVE LEAKAGE AND PROPER FUNCTIONING OF ON-OFF MECHANISM AND INDICATOR:

AT INSTALLATION AND AT SOURCE REPLACEMENT BY PERSONS SPECIFICALLY LICENSED BY THE NRC.OR AN AGREEMENT STATE.

THEREAFTER, TESTING SHALL BE DONE AT NO LONGER THAN-3 YEAR-INTERVALS, USING PROCEDURES

' STATED IN THE INSTRUCTION MANUAL.

LOJS,- THEFT OR TRANSFER OF THIS DEVICE AND FAILURE OF OR DAMACS TO THE SHIELDING, OR THE SOURCE CONTAINMENT, MUST BE REPORTED TO THE NRC OR AN AGREEMENT GTATE.

THIS' LABEL SHALL LE MAINTAINED ON THIS DEVICE IN A LEG 7BLE CONDIYIOF, REMOVAL OF THIS LABEL'IS PROHIBITED.

RS-115 (0289)~-

Page=9 UNITED STATES NUCLEAR REGULATORY COMMISSION-RULES and REGULATIONS TITLE is. CHAPitt 1. CODL OF f f ormat asCULATtoNS-tNtmov PART 31 e GENERAL DOMESTit.; LICENSES FOR BYPRODUCT MATERIAL Tthe purpose of detecting, mes.suring, 2 gauging of controlling thickness, den.

E sity, level, interface location. rad 34 l atton, leakage, or qualitative or quanti-6 tative chemical composition, or for

  • producing Ught or an ionized atmos.

(phere, (b) The general Ucense in paragraph (a) of this section applies only to by-product material contained in devices '

which have been manufactured or ini-o E tially transferred and labeled in ac-

  • cordance with the specifications con.

E tained in a specific Ucense lasued pur-

maant to i 32.51 of this chapter or in accordance with the specifications contained in a specific Ucense tasued

' i by an AgTeement State snich author.

taas distribution of the devices to per-sons generally licensed by the Agree-

. ment State,

(' c) Any person who acquirea, re-I ceives, possesses, uses or transfers by-product material in a device puuant J to the general license in paragraph (a) of this section: '

(1) Shall assure that all labels af-fixed to the device at the time of re-j ceipt and bearing a statement that re -

i moval of the label la prohibited are

.. maintained thereon and shall comply 0 wit.'s all instructions and precautions O provided by such labels; -

r (2) Shall assure that the device is

- ' tested for leakage of radjonct!ve mate--

2[

a rial and proper operation of the onoff mechantam and indicator,if any, at no j

lenger than six month intervals or at l

such other intervals as are specified in' l-the label; however:

(1) Devices containing only kr}Tton -

1 l:

need not be tested for leakage of ra-j dioactive material, and (11) Devices containing only tritlum mP-

_8 31.5 Certain enessuring, gauging or con-

.or not more than 100 microcuries of trolling devices other beta. and/or gamma emitting I

(a) A genere'!jcense is hereby issued material or j

= to ecmmercia) and industr1A1 firms and i

researuh, eduentional and medical in-l

' stttu;1oc.s.- Individuals in the conduct i

[ of thair business, and Federal, State or

. local government agencies ti acquire.

  • receive, possess, use or transfer, in ac-cordance with the provtstons -f pars-graphs (b), to and (d) of this section, j

byprod e

'* rial contained in de-vices desi% und ras.nufactured for

' Persons possessina brproduct :naterialin devices under the general itemose Mn i 313 i

tutore Jut 15,1s75, snar mottnue to sxsw sess use or traAster that materialin accord-

.l ance vt'h the requirement; of (%S in M

ef fect on Ja.n.14, ISTS.

4-t Gl

n RS-115,(0289)

. Pa ge.10 PART 31_e GENERAL DOMEST1C LICENSES FOR BYPRODUCT MATERIAL 10 micrecuries af alpha emitting material ' mission Inspection and Enforcernent and devices held in storage in the original Regional Office I sted in Appendix D of shipping container' prior toinitialinstalla.jPart 20 of this chapter, a report contain-tion need not be tested for any purpose;png a brief description of the event and (3) Shall assure that the tests requireds the remedial action taken; by paragraph (cX2) of this section andI (6) Shan not abandon the device other testing, instauation, servicing, and containing byproduct material; removal from installation involving the

' radioactive materials, its shielding or;p

(?) Shau not export the devue containment, are performed:

  • containing byproduct material except in i in accordance with the instructions; accordance with Part 110 of this

. l pro (v)ded by the labels;or i

7 chapter; (ii) by a person holding a specific " (8) Encept as provided in paragraph

. license pursuant to Parts 30 and 32 of (c)(9) of this section, shall transfer et R this chapter or from an Agreement State dispose of the device containing b y-to perform such activities; product rnaterial only by transfer. to a s

,s (4) Shau maintain records showing person holding a specific license pursuant -

Y

- compliance with the requirements of to Parts 30 and 32 of this chapter or from f

paragraphs (cX2) and (c)(3) of this sec-an Agreement $!*te, to receive the device 4

tion. The reFords shall show the results of and within 30 days after transfer of a tests. The records also shall show the device t? a specific licensee shall furnish dates of performance of, and the names to the Director of Nuclear Material Safety of persot: performing, testing, installa' and Safeguards, U.S. Nuclear Regulatory tion, servicing, and removal from installa-Comrnission, Washington, D.C. 20$53, a tion concerning the radioactive material, report containing identification of the

_its shielding or containment.

device by manufacturer's name and

~

Records of tests for leakage of radio-model number and the name and address active material required by paragraph of the person receiving the device. No

. (c)(2) of this section shall be maintained report is required if Oe device is trans-for one year after the next required leak ferred to the specific licensee in order to '

test is performed or until the sealed obtain a replacement device; source is transferred or disposed of.

(9) Shall transfer the device to j Records of tests of the on off mechanism.another generallicensee only:

e and indicator. required by paragraph g (i) Where the device remains in use at 2 (c)(2) of this section, shall be maintained va particular location. In such case the

- for one year after the next required test Stransferor shall give the transferee a copy I of the on-off mechanism and indicator is q f this section and any safety document; performed.or until the sealed source is identified in the label of the dev;> v transferred or disposed of. Records which within 30 days of the transfer, repa tr j

are required by paragraph (c)(3) of this the Dire, tor of Nuclear hfaterial Saht:

' ~

section shall be maintained for a period and Safeguards. U.S. Nuclear Regulatory of two years. from the date of the Commission, 4 ashington, JC, 2055 5, recorded event or until the device is th manufa, rer's name ' and model transfertu or disposed o number of dence transferred, the name and address of the transferee, and the

($- 'Jpon the t.currence of a failure name and/or position of an individual of or oamage to, or any Indication of a who may constatute a point of conta.t -

possible failure of or damage to,' the between the Commission and the trans-

!(

shielding of the radioactive material or feree; or the on off mechanism or indicator, or (ii) Where the device is held in storage

upon the detection of 0.005 microcurie in the onginal shipping container at its -

g or more removable radioactive material, intended location of use prior to initial

shall immediately suspend operation of use by a generallicensee.
  • the device until it has been repaired by [~

R the marufacturer er other person holdmg (10) Shall comply with the provisions

~

a specific license pursuant to Parts 30 and ;of Q { 20 402 and 20 403 of this chapter 32 of this chapter or from an Agreement ifor reporting radiation incidents, theft or State to repair such devices, or disposed gloss of licensed material, but shall be of by transfer to a person authortaed by a,, exempt from the other r?quirements of specific license to receive the byproduct (Parts 19,20.and 21 of this chapter, material contained in the device and, 7 (d) Tie general bcense in p2ragrapr -

within 30 days, furnish to the Dtrector of N a of this section does not authorize tht the appropriate Nuclear Regulatory Com ; (m)anufacture or import ' of devices

$ containing byproduct material-r, y.

=

f RS 115-

Page111 PART 30 e RULES OF GENERAL APPUCABluTY TO DOMESTIC UCENSING--

s I

(d) Each license issued pursuant te the regulations in this part and Parts -

3135.39shall be dee.ned to contain the provisions se' forth in se: tion 183b. d.,

inclusive, of 4 a Act, whether or not '

these provisions are expressly set forth in p the license.

E (e) The Commission may incorporate,

& in any license inued pursuant to the g regulations in this part and Parts 31 35.39 at the tirne of hsuance, or thereafter by =

appropriate rule, regulation or order, such additional requirements and; conditions with respect ' to the licensee's receipt.

P-possession, use and transfer of byproduct L

material as it deems appropriate. or

_necessary in order to:

a.

(1) Promoq the common defense and

~

securityl (2) Protect health or to minimize y

danger to life or property;

'g (3) Protect restricted data; -

'(4) Require such - reports and the

[ Yeeping of such records, and to provide' 4r such inspections of activities under g the license. as may be necessary or

'$ 3 0,3 4 Te rms - and conditions of appropriate to effectuate the purposes of the Act and regulations thereunder, licenses.

. (a) Each license issued punuant to the regulations in-this part and the regula-tions in Parts 3135.39shall be subject to F

all the provisions of the Act, now or hereafter in effecs, and to all-alid rules, regulations and ora s of the Com-f rnission.

(

- (b) No license issued or granted pursuant to the regulations in this pa:t and Parts 3135,39 nor.any right under a license shall be transferred, assigned or in any manner disposed of, either volun-t arily or involuntarily, directly - or indirectly, through transfer of control of any license to any person, unless the Commission. shall, after. securing full h information, ftnd that the transfer is int-g sccordance with the provtsions of the Act g and shall give its consent in writing.

-(c) Each person licensti by the Com-mission pursuant to the regulationsin th.s part and Parts 3135,39shall confine his possession and use of' the byproduct.

material to the locations and purposes authorized in the license. Except as other-ws::e provided in the license, a license issued pursuant to the regulations in this

~

part and Parts 3135.39of thischapter shal' carry w,th it the right to receive, acquire

own, and possess, byproduct materias.

Preparation for shiprnent and transport of byproduct msterial shall be in accordanct with - the provisions of Part 11 of this chapter.

I

Rv115:(0289)

Page 12 PART 30 e RULES OF GENERAL APPLICABILITY TO DOMESTIC LICENS!NG-RECORDS,1NSPECTIONS, TESTS, 7 30.52 Insentiom.

initial report shall be followed within AND REPORTS (a) Each licensee shall afford to the a period of fif teen (15) days by a writ.

Commission at all reasonable times op., ten report submitted to the appropri.

b portunity to inspect byproduct materi. ; ate NRC Regional Office thich sets o

p 30.51 Records.

al and the premises and f acilities l forth the details of the incident and

=

s of su w rit (a) Each pe rson who receives by-

[ wherein byproduct material is used or g i eons [qu nc s Cop product material pursuant to a license w stored.

. of Inspection and Enforcement. U.S.

(b) Each lleensee shall make availa-issued pursuant to the regulations in this gg _ gg

,g g

a o

C Wa.shington. D.C. 20555 part and Parts 3135,39shall keep records na o

r od ept showing the receipt, transfer, and by him pursuant to the regulations in disposal of such byproduct material.

1his chapter.

Subsequent (b) Records which are required by the to the submission of the. written rep rt required by this paragraph. the regulations in this part and Parts 31 35.39 $ 30.53 Tests.

licensee - shall promptly inform the or by license condition shall be Each licensee shall perform, or Office of Inspection and Enforcement maintained for the period specified by h permit the Comrnission to perform, !; by means of a written report of any -

additional information, k such tests as the Commission deems O substantive the appropriate regulation or license appropriate or necessary for the ad a which becomes available to the licens-condition. If a retention period is not otherwise specifie d by ' regulation g n ministration of the regulations in this y ee, concerning an attempted or appar.

ent thef t or unlawful diversion of tri-part a,nd Parts 31-35 and 39 of this a

license condiu.on, such records shall b*.

chapter, including testa of; tium.

maintained until the Commission (d) The reports described in this sec.

tion are not required for tritium pos-authorizes their disposition..

(a) BYpr duct material; sessed pursuant to a general license (c)(1) Records o; receipt of by.

(b) Pacilities wherein byproduct ma-provided in Part 31 of this chapter of product m a te rial which must be a, terialis utilized or stored; fof tritium contained in spent fuel.

n maintained purruant to paragraph (a) of (c) Radiation detection and monitor this section shall be maintained as long as l ing instruments; and the licensee retains possession of the q (d) Other - equipment and devices Ith Lh' "tIIi**ti "

byproduct material and for two years

"d I" * ""'#t'.." "ict material.

or storage of t'.

following transfer, or disposal of the byproduct material. (2) (Deleted 43 FR 6915.) (3): Records of transfer of by.

j h

(e) (reserved) q roduct material shall be maintained by a 6 30.55 Tritium reports.

s p

h the licensee who transferred the material E ta) (Reserved:-

0

[8, for five years after such transfer. (4) !

g Records of disposal of byproduct ma-

~

~

terial shall be maintained in accordance with $ 20.401 (c)of this chapter.

. ( d )(1 ) Records which must be main %ined pursuant to ' this part and Parts 3135,39may be the original or a reproduced copy of microform if such reproduced copy or microform is duly e

authenticated by authorued personnel $

and the microform b capable of ;

(b) [resen ed]

rnducing a clear and legible copy after 6-s rage for the period specified by Com. O mission regubtions.

(2) If there is a conflict between the Commission's regulations in this part and Parts 3135.39ticense condition, or other written Commission approval or author-ization pertaining to the retention period for the same type of record, the retention

~

tc) Exce t s.s a ecified in paragraph period specified in :he regulations in this (d) of this section, each licensee who is 1 part and Parts 3135,39for such records authorized - to possess tritium shall shall apply unless the Commission, report promptly to the appropriate NRC Regional Office listed in Appen-pursuant to Q 30.11, has granted a o

specific esemption from the record reten-

dix.D of Part 20 of this chapter by e telephone and telegraph. mallgram, or tion requirements specified in the reguta-a f acsimile any incident in which an at-Jions in this part or Parts 31 35.39.

' tempt has been made or is beltaved to

' have been made to commit a thef t or unlawful diversion of more than 10 curies of such material at any one time or more than 100 curies of such materialin any one calendar year.The i

-_w

o

,w-RS-115 (0289)

Page 13 i

' PART 30 o RULES OF GENERAL APPLICABILITY TO DOMESTIC, LICEN.31NG-

~

ENror CrMENT -

penklty imposed pursuant to,section 234 of the Act for vioistion of section 8 30.61 Modification and revocation of li-50, 57, 62, 63, 81, 82, 101, 103. 104. 10*l, tenses or 109 of the Act, or section 206 of the C (a) The terms and conditions of each Energy Reorganization Act of 1974, or

$ license issued pursuant to the regula. any rule, regulation, or order issued I

r tions in this part and Parts 3) through : thereunder, or any term, condition, or A 35 of this chapter shall be subject to = limitation of any license issued there-

amendment, revision or modification [ under, or for any violation for which a by reason of amendments to the Act, o license may be revoked under section or by res. son of rules, regulations and ' 186 of the Act. Any person who will-orders issued tri accordance with the fully violates any provision of the Act terms of the Act.-

' or - any, regulation or order issued

~

thereunder may be guilty of a crime and, upon conviction, may be punished (b) Any license may be revoked, sus-by fine or imprisonment or both, as pended or rnodified in whole or in provided by law.

part, for any material false statement in the applic' *.lon or any statement of fact requ! red under sectionr182 of the Act, or because of conditions revealed by such application or state'nent of f act or any report, record or inspection or ether means which would warrant the Commission to refuse to grant a 11, cense on an original application, or for

,, violation of, or failure to observe any

  • of the terms and provisions of the Act

,= or of any rule, regulation or order.of

[ the Commission, (c) Except in cases of willfulness or o* those in which the public health, in-terest or safety requires otherwise, no license shall be modified, suspended or revoked unless, prior to the institution v

. of proceedmts therefor, facts or con-duct which may warrant such action shall have been es'ted to the attention of the licensee in criting and the li.

censee shall have been accorded an op-portunity 'to demonstrate or achieve compliance with all lawful require.

i

_ments, C

E 5 30.62~ Right to cause the withhi>tding or a

recall of byproduct material.

OL

~

The Commission may cause the withholding or recall of byproduct ma-terial from any licensee who is not

,. equipped to obsttv Or falls to observe

= such safety ' standards to protect E health as may W established by the a Commission, or who uses such materi-

.I als in violation of law or regulation of

  • the Commission, or in a manner other than as disclosed in the appit:ation 1

therefor or approsed by the Commis-

_sion.

3 30.63 Violations.

order An injunction or othe

'I may be obtained proh%.

any Vola-

. tion of any proviin L

! the /'

  • P s' Energy Act of 1954 is amen rd, or I Title !! of the Enern Reorr*.zataon
  • Act of 1974, or any tentar a at order tasued thereunder. A co,;,rt vitlee may be obtained for tue payment of a civil

. cia

RS-115 - (0289).

o Page 14-c,

. PART 20

  • STANDARDS FOR PROTECTION AGAINST RADIATION:

uals, circumstances under which the [ (b) Twenty.fourhournotificction.

exposures occurred, and the extent of ; Eachlicensee shall within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of possible ham.ard to persons in-unres' 2 discovery of the event. report any event (5 Actio which have been taken. E "8 #* "" **

  • E """ '

or wlU be taken. to recover the materi.. by the licensee that sney have caused or

_1, threetens to cause:

I, al; andProcedures or measures which

- (1) Exposure of the whole body of l

(6)

' have be;, or will be adopted to pre-E tent a recurrence of the loss or theft any individual to 5 rems or rnore of ts.

dittion; exposure of the skin cf the A of licensed material, whole body of any individual to 30_

(c) Subsequent to filing the written report the licensee sht!! Elso report

, rems or more of radiation; or exposure.

Any substantive additional informa, of the feet, ankles hands, or forearra i tion on the lor: or theft thich be a to 75 nms or mon of radladon: or..

L comes available to the licensee, within e.

(2)The release of radioactive materi.

~

30 days after he learns of such infor. O alin concentrations which. if averaged -

mation.

over a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.. would (d) Any report filed with the Comt exceert 600 times the limita specified mission pursuant to this section shall for such materials in - Appendix B.

.s be so prepared that names of individ-Table II of this part; or

'~

utis who may have received exposure (3) A loss of one day or more of the-to radiation tre stated in a separate operr.tlon of any facilities affected; or

.,ptrt of the report.

q

" (e) For holders of an opereting license I

$ $2.000.(4) Damage to property in exce for a nuclear power plant the events included in paragraph (b) of this section g must be reported to accordance with the procedures ducribed in i 50.73 (b). (c). -

L (d). (e), and (g) of this chapter and must

[* (c) Any report filed with the Comk '

1 include the information required in R mission pursuet to this section shall t

  • I30.403 Reports of theft er lose of Paragraph (h) of this section. Events 8 be prepared so C't names of individ-acensed meterteL reported in accordance with 5 5053 of s utis who have* received exposure to ra.

(e)(1) Each licensee shall report to the this chapter need not be reported by a

" dittion will be stated in a separate 1 Commission, by telephone, immediately $ duplicate report under paragraph (b) of

{,part of the report.

this section.

f after it determines that a lou or theft of 2 p

licensed material has occurred in such a g so.aos neeeeen no et incusenes, response to the requirements of this s and dru circum ances section must be made es follows:

gu g'

(a) /mmedicte notification. Each

-(1) Ucensees that heve en installed.

licenne shallimmediately report any substantial hazard may result to persons event 8 involving byproduct. source, or E:nergency Notificetion System shall f ;in unrestricted areas, e

d is7e (2) Reports must be made as follows:

[Ch* "CI'(('[fh used nd o

nt te C

(i) Ucensees having an installed threatens 16cauu:

2 Operations Center in accordance with s Emergency Nott5 cation System shall t1) Exposure of the whole body of a' l 50J2 of this chapter m-

make the reports to the NRC Operations any individual to 25 rems or more of '. (2) All other licensees shall make the Center in accordance with 150J2 of this radiation; exposure of the skin of the ' reports required by paragraphs (a) and -

chapter. -

whole body of ar.y individual of 150 (b) of this section by telephone and by (11) All other licensees shall make rems or more or radiation; or exposure telegram. mailgram, or fecalmile to the reports to the Administrator of th*

of the feet, ankles, hands or forearms Administrator of the appropriate NRC.

appropriate NRC Regional Office listed

.of any individual to 375 reme or more

- Regional Office listed in Appendix D of in Appendix D of this part.

, of radiation;or this part.

(2) The release of radioactive ma'.eri-(b) Each licensee who maku a report e.

undet paragraph (a)of this section shall. E al in concentrations which. If averaged over a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. would within 30 days after teeming of the loss of theft, make a report in wnting to the exceed 5.000 times the limits specified.

U.S. Nuclear Regula tory Commission.

for such' materials in Appendix B.

Document Control Desk. Washington.

Table II of this part; or D.C. 20555, with a copy to the (3) A loss or one working week or appropriate NRC Regional Office listed more of the operation of any facilities in Appenda D of this part.The report

. af fected; or

,,,sbell inchde the following information:

f

{terial involved. including kind quantl*

  • a200.000.(1) A description of the beensed ma 6 (4) D k ty, chemical, and physical form; a - (2) A - description of the circum. =,,,,

a stane*s under which the loss or thef t '

, occurred.

(3) A statement of disposition or a

probable -disposition of the licensed material involved; (4) Radiation exrosures to individ-

-+ =

RS-115 (0289) 1 Page 15 n

PART 20

  • STANDARDS FOR PROTECTION AGAINST RADIATION APPENDIX D,-UNITED STATrs NilCLdAR REGULATORY COMMsSstos REGIONAL OFFICES h*[

A c esses s

Regon t Conneicttxt Dolamere, Dsuct e1 Ccest(ma, Maine, USNRC,475 Allendale read,C,, v. i 421:13'37-5000

. Maryiand, Massachusetta, New Hampanire, New Jersey, New Frussia, PA 19400.

(FTS) 488-1000 i

Ycyk, Pennsylvarua. Mtodo (Wand, ard Vermont.

USNRC, 101. Mane %a ' Street, NW.

(404) 221-4503

. $ Regon it Nabama, Florda, Georga' Kentxty Masasopi. Norm SJits 3100, Ausnta, GA 30321.

(FTS) 242-4dO3 Carchna. Puerto Reo. Soum Carolw a. M.nessee, V<gna, v-

$. Ytyn IslarvM, and West Vrgitu

', s USNRC, 799 Roossett Hoaci, Glen (312) 790-5500 Megon HL libr.oss, induna, lows, Ms:fugan, MA.,sota, b.saci.n.

Ellyn,IL 60137, (FTS) 388-5500 g

Ormo, and Wrecor,asn.

Repon IV: hkarnas, Colorado, Idaho, Kansas, t tx4w.a. Mon.

USNRC,611 Ryari PLua Dnve, Suste (617) 864 6100 u.

taru, Nebraska. New Meuco. North Dakota,06latma, Soum HDO, Arkngton, TX 7C011, (FTS) 728-8100 g

in Oakota. Texas, Utan, and Wyortung Hopon IY; Fieks Office

.h USNRC, Region IV Uredum Recovery (303)236,2805 Tw*d ONee, 730 S,mrfis Sonet, (F(S) 776 2005 F.O Bot 25325, Denver, CO 60225.

Begion V: Naska, Artrona. Caldomia. Hawan, Neve.a. Orapn, USNRC,1450 Mana Lane, Sota 210, (415) 943-3700*

Watnut Creek, CA 94596.

(F7S) 483-.3700 Pache Trust Temtenes, are Washingun i

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  • OtJ CONDITIOt4" WARtilt4G LABEL

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FOR USER'S POWER.

1/2* (13mm) NA THREADED ROD I'./.

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  • IPS CONDUlf BY USER)

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OPERATING HANDLE IN *OFF" POSITIOrd PREFERRED ut..?4Tir4G 15 ON VERTICAL PIPE WITH PROCESS FLOWir4G UPWARDS

- 10" (254mm) 37-p;pg

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(432mm) 0.0.

(299mm)

APPROXIMATE WElGHT OF.MEASURANG ASSEMBLY IS 190 LBS. (86 Kg.).

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Amendment No. 01 1

I j Cancer Treatment Center Partners l

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I In accordance with letter dated February 6,1990, License Number 34-25978-01 is amended I

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Cancer Treatment Center Partners I

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4 is-granted for no more than 30 days for. any one cource change.-

(19.Thelicenseeshallmaintainrecordsofinformationimportanttosafeandeffectiv dcrommissioning at the address-specified in Condition 10. per the provisions of P

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For the U.S. Nuclear Regulatory Commission y

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Date March 16. 1990.

By-Cassandra F. Frazier k:

MaterialsLicensingSection, Region 511 3rj c

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EXP. DATE: 19941130 O

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APPLICANT / LICENSEE: UC ANCE.c TRE ATMENT2 CENTERgfARTNERS

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SIGNEo DATE

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lAAR 161990 Cancer Treatment Center Partners i

ATTN: - William-F. Demas, M.D.

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Radiation Safety Officer 2376 Benden Drive Wooster, OH 44691 Gentlemen:

Enclosed is Amendment No. 01 to your NRC License No. 34-25978-01 in accordance with your request, acknowledging.the adequacy of your teletherapy survey

report for your recently installed unit.

Please note that we have changed the name and address on your license from-

[

your home address to that of the facility now that it has been constructed and-also have corrected the street name and= number from 2375 Benden to 2376 Benden, Drive, in accordance'with your request during-our telecon on March 8, 1990.

If any of'this information is not correct, please notify me promptly.

Note also the addition of License Condition Numbers 18. and 19.

Condition 18.

provides you with an exemption from decommissioning' requirements for those

times when you may possess more than one source.

This condition is applicable

.for source changes only.,However, this does not relieve you of record keeping requirements relative to information which the: Commission considers important to decommissioning.

Therefore, we have added License Condition-19. requiring that you maintain such records as set forth in Section 30.35(g) (enclosed).

Pleasezreview: tie enclosed document carefully-and be sure.that;you understand all conditions'.. You must conduct your program involving radioactive. materials!

in accordance with the: conditions-of your NRC -license', representations made -in your license application, andLNRC regulations.

In particular,. note that'you must:

1. -

Operate in accordance with NRC regulations 10'CFR Part 19, " Notices, Instructions and Reports to Workers; Inspections " 10 CFR Part 20,

" Standards for. Protection Against Radiation," and other applicable 1

regulations.

2.

Possess radioactive material only in the quantity and form indicated in your license.

3.

Use radioactive material only for the purpose (s) indicated in your

-license.

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-4.

Notify NRC in writing of any change in mailing address.

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Cancer' Treatment Center Partners 2

5.

. Request and obtain appropriate amendment if you plan'to chh.ge ownership of your organization, change locations of radioactive material, or make any other changes in your facility or program which are contrary to your-license conditions or representations made in your license application and any supplemental correspondence with NRC. Any amendment request should be accompanied by the appropriate fee specified in 10 CFR Part-170.

6.

Submit a complete renewal application with proper fee or termination request at least 30 days before the expi ation date on your license.

You will receive a reminder notice-approxima*.iy 90 days before the expiration date.

Possession of radio.v no inaterial af ter your license expires is a violation of NRC regulatisas.

7.

Request termination of yo"- license if you plan to permanently discontinue activities involving radioactive material prior to your expiration date.

You will be periodically inspected by NRC.

Failure-to conduct your program in.

accordance with NRC regulations, license conditions, and representations in your license application will result in enforcement action against you in accordance with the General Policy and Procedures for NRC Enforcement Actions, 10 CFR Part 2, Appendix C..

If you have any questions or require clarification of any of the above stated information, contact us at (708) 790-5625.

Sincerely, Original Signed By L,ren J. Hueter Materials Licensing Section

Enclosure:

1.

Amendment No. 01

.2.

10 CFR Part 30 f

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CONVERSATION RECORD

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O vistT O CONFERENCE Q4ELEPHONE

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O IENNO Locat6on of Visit / Conference:

Q'DUTOOING MAME OF PERSON (S) CONTACTED OR IN CONTACT ORGANt2ATION (0mee, g Instee,

TELEPHONE NO.

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'U' 375-3557 i?f f a SUBJECT C A) 2 s 7/)2

SUMMARY

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NOME OF PERSON DOCUMENTING CONVERSATION SIGNATURE DATE l

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CONVERSATION RECORD ggr,rg,ggg so m -io

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February 6, 1990 Cancer Treatment Center Partners 2375 Benden Wooster, Ohio

' Materials Branch.ials Licensing Division of Mater U.S.-

Nuclear Regulatory Commission Region III 799 Roosevelt' Road

' Glen Ellyn, Illinois.60137 l

Ref:

License No. 34-25978-01 N

o Il

Dear Sir:

Enclosed is a copy of all calibrations and surveys related to the' installation of a reconditioned cobalt-60 teletherapy unit-in our I;

newly constructed facility.

Also enclosed is a copy of - our emergency procedures.

Installation of cobalt unit and required ancillary equipment (camera, mirror,-etc.) took' place during period 'through January 26,'1990.

Surveys and calibrations were conductedias permitted by.

progress of -installation.

The first patient was - treated ~ on

'l

-February 1, 1990.

_..y

.If-you have any questions, please feel free to contact the'cenior; radiological physicist on this project, Dr. Starchman~at (216).

494-7353, or the RSO/ Radiation Oncologist,. Dr. Demas at.(216)L 375-3557.

s 1

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-Sincerely yours, g

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FEB 151990 W

. William F.

Demas, M.D.

REGION III u

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.for Cancer Treatment' Center Partners g e Note:

'The above. signature on this letter, which is submitted as part of the report, also serves to fulfill the conditions of

'10CFR35 regarding signature of the report by the RSO, Dr. Demas.

-l coumot.NO. 8' 8.7 0 2 q

'j Medical Physics Services, Inc.

,4 5942 EASY PACE CIRCLE, N.W.

1 CANTON,01110 44718 I

216-494-7353 i

Wayne R. liedrick, Ph.D.

David L liykes, M.S.

C'nified Diagnostle Radiological Certified Radiological Physicist. ABR -

OM Wdb Nm M N'&

end Medical Nuclear Phyneist. ADR 216-438-6200 ( Aultman llorpital)

Louis R. Milavickas, Ph.D.

F "

  • H#8 Dale E. Starchman, Ph.D., President Clinical Radiation Biophysicists Cenified Radiological Physicist. ABR r

R:nald O. Johnson, Ph.D.

Certifed llealth Physicist. ABile Paul N. Shaaeen, M.S.

Susy Isaac Alunkal, M.S.

Cenified Thernicutic Radiological ?.

Physicist. ABR February 5, 1990 f

-(

William F.

Demas, M.D.

Cancer Treatment Center Partners 2373=Bendon Wooster, Ohio 1

l.,

Dear Dr. Demas:

f 1

L This constitutes a full survey and calibration report of results i

from. studies on the' newly purchased AECL Model 80 Cobalt-60 teletherapy unit installed in the newly constructed _ cobalt-60 l

Teletherapy Room of the facility operated by Cancer Center Partners L

at 2373 Benden in Wooster, Ohio.

u This unit was reconditioned as part-of the move from the location of-the previous owner.

The source was not changed, but the 5 year i

inspection and service was performed by Teletherapy Services, Inc.

as describedLin the attached certificate.

alibrations surveys and tests were performs d by the 4 Teletherapy Physicists listed-- on the NRC license for the facility (Dale E.

Starchman, Ph.D.,

Louis R.- Milavickas,-

Ph.D.,

Paul N.

Shaheen,-

M.S.,iand David L. Hykes, M.S.

All of these persons are. certified by the American Board of Radiology in areas which include the sub-specialty of therapeutic radiological physics in each case..

4. The. portions performed by each of these persons are described in the_ attached reports.

All of these surveys and'calibratioas were

. coordinated by m'e o, all results were reviewed by me, and the e

reports'were summarized and' signed by in e.

RECEIVED FEB 151990 FEB 15196 COMPREllENSIVE CONSULTIN

~

ON rasound e Wn ustry

  • Radiobiology *

' Therapeutic and Diagnostic Radioingy

  • Nuclear Medicine
  • M i
Teachms '. Depenmen' Ilesign. Cahbralism - Shielding Protection - Licensing - Equipment Selection and Acceptance Testing - Prograrnming - Resec r
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CONTROL No.48 8 7 0 2 oS.

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If you have any questions, please do not hesitate to call ~.

Sincerely yours, D' ale E. ; Starchman, Ph. D.

Certified by the American Board of Radiology and by the'American Board of Health Physics Note:

The enclosed letter to the NRC must be signed by'you and submitted with the entire survey and calibration report including this

.)

letter.

As per your license conditions these results must.be reported to the NRC 30 days following completion of the' new -

facility installation.

My interpretation, as reflected in the cover letter to the NRC, is that these materials, must be. received

~

by the NRC no later than 30 days from the last day'of changes--on the unit required as part of the move

'and. completion of-installation of required ancillary equipment.

The room and unit-installation including TV and mirror installation was completed on or-about January 26, 1990.

The first patient was then treated on February'1, 1990.

i i

^

h osures:

Full copies of report are enclosed for distribution as follows; i

Original for Dr. Demas Copy for file at facility

. Copy for NRC 2

i mNmot.NO. 8 8 'i 0 2 z

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ' ' - ~ ~ ~ -

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Radiation-Survey of Structural Shielding for Cobalt-60 Unit Performed personally by Dale E.

Starchman, Ph.D.

and Louis R.

Milavickas, Ph.D. working tcynther on site on Janaury 8, 1990 j

This unit has a beam stop.

The beam was. fully opened to 32 X 32 cm I

at 80 cm SAD with a tissue equivalent phantom large enough to intercept the-beam locate 6 at inocenter.

The unit was incrementally rotated through 360 degrees about the center of the phantom.

Measurements were made at all locations for worst case i

situations where beam was angled so as to r'esult in 30 degree scatter to achieve normal incidence on the barriers. A GM survey system, which provides high sensitivity and a short time constant no as to more readily identify any " hot spots"'was used.

The GM survey system consisted of a Ludlum Model 2 meter with a Model 44-6 probe.

The system was subjacted to a 2 point per scale calibracion by the manufacture on 12/20/89 using Cs-137. The survey system was tested with the built in check source before, during, and after completion of the surveys.

As an informational item only, it should be noted that in order to confirm results, several other meters were used, but the above noted GM was used for all results-recorded below.

- This unit has an integral beanstop.

The primary beam is restricted-to tha center of the b.amstop at all times.

All measurements were.

made for scattered radiation using a 32 X 32 cm field on the phantom as indicated above.

The following maximum values were recorded.

(See Figures I, and II enclosed).

Fig. I l-wall W-X

<0.2 mR/hr Wall X-Y

-<0.2 mR/hr

. wall Y-Z (includes 1/4" leaded-door and vindow)

<0.2 mR/hr wall Z-W

<0.2 mR/hr I'ig. II --

ceiling (all locations above cobalt area)

<0.2 mR/hr Floor is cement slab on grade with no occupancy or crawl space below.

1 r

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Occuoancvr Beam orientation Conditions. and Use occupancy j e shown on Figure I for informational purposes only. As demonstrated by the above maximum instantaneous exposure rates, the shielding.is'such that one can assume-full occupancy in all~ areas by non-occupationally exposed persons under worst case beam conditions with.use in-the " beam on" mode 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per week and still achieve exposure rates far below applicable standards (40 hrs / week X O.2 mR/hr = 8 mR/ week).

==

Conclusion:==

Room shielding resulted in worst case readings in all areas being below 0.2 mR/hr instantaneous rate under all operating conditions which is far below all applicable NRC standards for this unit.

No-changes in shielding are recommended.

Source Head Survev:

See source head survey attached.

Average exposure rate for the 14-b point survey was 0.96 mR/hr vs the legal limit of 2.0 mR/hr at-1 meter from the source and the maximum was 3.0_mR/hr vc the legal limit of 10.0 mR/hr.

This was completed on January 8, 1990.

Note on orientation:

-l

.i The enclosed diagram (Figure I) shows the room orientation as it j

actually exists.

The relationship between the cobalt unit and the

+

room is the same as shown in the design originally submitted and 1

the wall thicknesses are the same for this room and maze, which set-outside the. therapy center building, sharing the same common wall as originally designated.

However, in order to avoid confusion for anyone performlag a one-to-one comparison of the current print as constructed to the origintl print as designed, one must take the mirror image of the room, rotate it 90 degrees, and move'the door to a better shielded position nearer the maze wall.

Since the original design. permitted all areas on all 4 sides to allow 100%

occupancy by non-occupationally exposed personnel, these changes

.l affect only the-relationship to the compass, not the protection I

afforded by-the structural shielding.

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coNmol.No 8 8 7 0 2 1'

%f 1

-January-1990 I

L Head Leakage Survey. Data I

1)

License Holder:

Name:

Cancer Treatment Centers Partners i

Address:

320 N. Hometown Rd.

Akron, OH 44313 License #:

34-25978-01 2)

Surveyor:

Name:

L.R.

Milavickas, Ph.D.

Address:

4412 Satinwood Cr.

N.W.

Canton, Ohio 3)

Reason for Survey:

Installation of unit in newly constructed facility 4)

Installation of cobalt unit and required ancillary equipment (camera,. mirror, etc. ) took place during period through January, 26, 1990.

Surveys and calibrations were conducted as permitted by-

. progress of installation.

The first patient was treated on February 1, 1990.

5)

Date(s) Head and Shielding Survey Conducted:

1/8/90 Calibration Conducted:

1/8/90 1/15/90 Calibration Confirmed:

1/31/90 6)

Survey Instrument Used Manufacturer Name:

LUDLUM Model #:

  1. 2/ Probe 44-6 Ser. No. 70875 Calibration Date:

12/20/89 CAL Procedure:

Calibrated by Ludlum under State of Texas Calibration License No. LO-1963 Check Source:

side mounted check source 7)

Teletherapy Unit Manufacturer:

AECL Model #:

TH80

  1. of Unit:

205 8).

Teletherapy Source Manufacturer:

Neutron Products Inc.

Model #:

NPI-20-4200W 9)

Activity of Source (Ci):

2308 Ci Assay Date:

11/1/89 1

l

4 -~

u t

c Wooster Co-6'O-Unit Figure F 1-i TELETHERAPY HEAD SURVEY.

(Source in 0FF position.

Top View Showing.

Measurements taken one meter orientation y

from sourcel of Views A through O l.'L REAR Radletion Level Poeltion No.

(mR/ht) m 0.5 View A 1

2 1.O A tief t stdt 3

15 w/.

4 3.0 g

B pett front!

View B s

C (fronti fr tl

(.

y 0.4 1

f U*1 a

View A. Vertical View B. Vertical

]

from left side from lef t front Vlow C

-9 1.0-5 10

'F ar M-View D 11 y

age P@

G

.0 14 45' REAR j FRONT x

x

- Average value 95 3.0 Maximum value 3

1/8/90 Date of survey Ludlum #2 Vi*w C verticai

. view o vertical inetmment used from front from right front P.n l i b ra t k ri

/kh~

14

$*my,*,*7,[,* number Neutron Product Inc. NPI-20-420 0 e

of teleiherapy source A

'See report atg g

o.to of in teii. tion

) REAR OUTPUT 45.1 O RHM FRONT

/

/

E RMM X

x

\\

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f S'e'.*.*r'eUnY' Jan. 8 15, & 31 g

of 1990 F-7 CONmot NO. 8 8 7 0 2

s l

January 1990

}

Wooster Co-60 Unit Calibration of Output A Victoreen Model 500 Electrometer.and a Farmer Chamber (Model 2571) calibrated by K&S Associates, an AAPM approved Regional Calibration Laboratory, on 6/5/89 was used.

The exposure rate in air was 70.6 R/ min at 80 cm with a 10 X 10 cm field, average of two

.j calibrations performed on Jan 8 and Jan 15, 1990 by Louis R.

Milavickas, Ph.D.

whose ABR certification includes therapeutic radiological' physics.

Area factors were measured for field sizes from 5 X 5 through'32 X

~

32.

Comparison of a3 minute exposure to three exposures of 1-minute each showed an average shutter tiv.e correction of -0.013 minute.

This was considered in calculat.:

of exposure rate.

Wedge factors for the available wedges (two 45 degree Wedges) were I

L measured and found to be within expected values.

Output was measured at 65, 80 and 100 cm with collimators set at.a.

fixed solid angle.

Output was found to follow inverse. square law over this range to within 1%.

Output was measured over 360 degree rotation of C arm in 90 degree increments and found to remain constant within less than 1% at isocenter.

i The solid-lucite trays used to hold or mount blocks attenuate the i

beam by 3.5%.

. Output'in terms of exposure at indicated distance and absorbed dose in small volume water were calculated according to the attached procedure.

Predicted output was then calculated on a monthly basis.

for future years using a computer program.

A copy of the results have been supplied to the facility.

'These values n.ust be multiplied by area factor and then by either TAR or by %DD X BSF to obtain dose rate.at a depth in a patient.

j' l

Temperature and-pressure corrections were made for all measurements.

R.C.L.C.F.

for chamber and reader = 0.951 Indeoendent Confirmation of Outouta l

On January 31, 1990 David L. Hykes, M.S. and Paul N. Shaheen, M.S.

L (both-of whom are certified by the American Board of Radiology in o

sub-specialties including.

therapeutic radiological physics) independently verified that output was within less than 1% of above value using a different properly calibrated electrometer and chamber which has been subjected to multiple cross comparisons with

.other dosimeter systems and radiation sources.

2

1 Wooster Co-60 Unit January 1990 Test Results i

l Timer constancy and linearity were checked over the range of 0 -

3.0 minutes.

The timer operates properly.

The light distance indicator was checked for 70, 80 and 95 cm.

It was found to be accurate within 0 mm when compared with direct measurement with the metal rod at 80 cm and within 3 mm at 95 cm i

and 3 mm at 70 cm.

Actual measurements were 80, 94.7, and 69.7 cm.

A pointer was placed at 80 cm from the source and the source distance was meas" red over 360 degrees.

The distance remained constant with i

mm which is excellent and meets the manufacturer's speci.! cations of i 1 mm.

Rotation of the collimu system about its axis changed the 1

indicated field size or position of the crosshairs over the e

entire range (90 degrees; unrough 270 degrees by less than 1 mm.

The collimators were adjusted to field size dimensions of 10 cm X 10 cm at 80 cm.

A 17" X 14" Kodak RP-V film then was placed 80 cm from the source.

The indicated light field was marked using pressure on the film package.

The film was exposed and developed.

Correspondence between light field and radiation-field was found to be excellent.

Field was found to be uniform using a densitometer.

This was repeated for a 30 X 30 field for a film placed at 80 cm L

from the source with the same correspondence and uniformity.

The light field measured within

<1 mm of the numerical collimator setting for fields of 5 X 5 cm to 32 X 32 cm.

The back pointer and cross hairs are aligned within 2'mm.

The couch rotates with a 3.5 cm sphere about the isocenter over 180 degrees of couch-rotation. Therefore, large angle rotations of the couch would shift the location of the CAX relative to patient anatomy.

l.

The lasers were adjusted and all pass through isocenter.

Overall impression of this unit (with the exception of couch rotaion) is that the mechanical precision cf the unit is good.

L l

3 i

1.

CONm0LNo. 8 8 7 0 2

a W

Wooster Co-60 January 1990 Safety Checks Leak Test Moistened Q-tip was used to wipe the source head and the inside 1

surface of the collimators.

Q-tip was checked'on GM counter first-to establish that no detectable radiation was present.

The Q-tip

+

was counter in a calibrated NaI crystal utilizing a scaler.

Comparison with a calibrated Cs-137 check source showed that the transferable contamination on the leak test was at least 10 times smaller than the allowable standard of 0.005 microcuries.

This was completed December 14, 1989 by Louis R.

Milavickas, Ph.D.

Interlock and Licht System h

The door interlock system was checked with a survey meter.

If the door is opened during an exposure, the source moves to the off position and can only be returned to the on position by using the control switch.

The door interlock system was shown to cause the source to return to the "off" position by monitering the "on-off" indicators and a radiation detector placed inside the room then-making soveral exposures, each was terminated by opening the door.

Source would-not return to "on" position until timer was reset.

The radiation monitor in the Co-60 room was checked for proper operation by turning the beam on, and observing that the monitor flashed red. When the door was opened the monitor stopped flashing red.

This monitor operates properly.

Beam on and beam off signal lights on the source head, cobalt room door, and control panel operate properly.

Emergency button at control panel operates properly. The emergency button device was to cause the source to return to the "off" position by monitoring the "on-off" indicator and a radiation-detector placed inside the room then making several exposures.

Source returned to the '_'off" position and will not return to "on" l

position until timer is reset.

Viewina System A TV system is,used to view patient.

The backup system is a mirror.

4 i

m; i

l..

~,

^

+

Wooster Co-60 January-1990

?

Safety Checks

'i i

t AgAm~ Limitation

-The unit does have an integral beam stop.

C arm rotates. 360 degrees.

The source head cannot rotate.

A set screw has the head fixed such that the central ray always points to the center of the beam stop.=

4 Also, the relay -. that allows for head swivel' has been. removed.

Therefore,-the'Co-60 beam is always intercepted by the beam stop.

i Emercency Instructions Emergency-instruction are posted (copy attached).

.A

" Caution.

Radioactive Material" sign is posted.

A " Caution High Radiation Area" ' sign is posted.

k 6

5 r.ONGOL NO. 887.02-

4 0

6 s

Wooster Co-60 Unit January 1990' Calibration Procedure for Determination of Dose Rate in Rads / Min

~

Co-60

, +

For an SSD = x cm 3

Dose = (E) (f) (Aeq) (

x

)

x + 0.5 For an SAD = x cm t

Dose = (E) (f) ( Aeq) i J

Where dose in these cases represents dose at-the center of a~small sphere of water just sufficient in radius to establish secondary _

electron equilibrium without backscatter; and where:

E = exposure-rate in roentgens / min in air at a distance x f = roentgen to rad factor for water (0.967)

  • Aeq =-fraction of radiation transmitted through the equilibrium thickness.(0.989)*

l l

.*0utput actually based ~on TG 21 values.

!~

6 L

1 l

}

l Emergency Procedures for Beam control Failure or Malfunction If the light signals or beam-on monitor indicate that the beam control mechanism has failed to terminats the exposure at the end of the preset time (e.g. if the red light stays on and the-green light is off, or if both the red and the green lights stay on for more than a few seconds), the source may still be in the on position.

The operator shall not attempt to manually close the source drawer because normally the time and exposure required-to i

remove the patient ano secure the area will be less than that required to attempt tc close the drawer.

The following steps are j

to be carried out r:omptly and in a calm manner by the Radiation Therapy Technologist:

1.

Open the door to the treatment room.

2.

If-the patient.is ambulatory, tell him or her to get off the table and leave the room.

3.

If the patient is not ambulatory, enter the treatment room but avoid exposure to the direct beam.

Pull the treatment table as far away from the direct beam as possible.

Transfer the patient to a l

stretcher and remove the patient from the room.

l 1

4.

Close the door and secure the area by locking the door to the i

treatment room.

-j.

5.

Turn off the main switch at the control panel.

6.

Notify the radiation therapist, radiation safety officer, and toletherapy physicist at once.

7.

Conspicuouly post a sign in the area to warn others of the i

problem.

8.

In addition to the above, unless there is some other critical

-factor such as a serious hazard to the patient, the operator should personally guard the door until the RS'J, teletherapy physicist, or manufacturer's representative is physically present.

- i CONEOL No. 8 8 7 0 2

E I

'U 7't

.e Emergency Procedures for Beam control Failure or Malfunction (continued) f s

i Radiation Safety Officer / Radiation Therapist:

William F.

Demas.

M.D.

Phone No.:

On Duty 375-3557 Off Duty 2t b - 4 3 4-O V bP i

Alternate Radiation Therapist:

Michael J.

Seider.

M.D.

Phone.No.:- On Duty 375-3557 Off Duty 2/b 43V-cy6>

Teletherapy Physicists:

Call any of the following teletherapy physicists whose location -is known (Paul' N. Shaheen, M.S., Louis R.

Milavickas, Ph.D.,

David L.

Hykes, M.S.)

and call Dale E.

Starchman, Ph.D. at 216-494-7353 day or night.

Messages may be left but continue calling all teletherapy physicists until one is personally made aware of the situation.

L 4

i t

$f?

e.'

1 Therapy Services Incorporated Five Year Inspection Certificate l-l-

This is to certify that the A.E.C.L.

Cobalt-60 teletherapy unit, Model No. '1heratron 80 Serial No. 205 located at Cancer Treatment Center Partners, 2375 Benden

-l Drive, Wooster, Ohio was inspected and serviced on j

brreMhM 17.-13,19 V9 by J % L. W rLE to assure the proper function of the source drive mechanism as authorized by Maryland Radioactive Materials License Number MD-21-009-01.

Edk Date l 2-13 -99 Signed V

4 Parts Used L,t STED C43T5( See.uiCE.PFrcCh b/cT(3) l l - ( 3-79

\\

Recommendations for future service

(

i-I Iurther. certify, that Therapy Services Incorporated, Source Drive Mechanism Servicing Procedure 1001 or 1002 was followed.

(

Date

12. - \\ 3-D Signed J'

V 4

TSI Form 103

(

doNmotNo. 8 8 7 0 9 i

.