ML20148H208

Requests Addl Info Re Application Requesting to Register Facility Profile Thickness Gauge Model 5245

ML20148H208
Person / Time
Issue date:	10/22/1990
From:	John Lubinski NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:	Engelhardt S ENGELHARDT & ASSOCIATES, INC.
Shared Package
ML20148G975	List: ML20148G974 ML20148G979 ML20148G994 ML20148H025 ML20148H043 ML20148H208
References
SSD, NUDOCS 9706090275
Download: ML20148H208 (20)

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'3j NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555

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October 22, 1990 Susan J. Engelhardt Lorenz & Engalhardt '

1626 Fordem Ave. #201 Madison, WI 53704

Dear Ms. Engelhardt:

This letter is in reference to your application dated June 8,1900 requesting i to register IMS's Profile Thickness Gauge Model 5245. The gauge is currently l being reviewed but in order to complete the review, the following information  !

is needed: I

1. Further details of the prototype testing and quality assurance checks  ;

which are performed on the safety features of the device (i.e. spring  !

shutter closing mechanism, air / electric failure detector, mechanism for automatically closing shutter when device is retracted or knocked over, the rail system whicn the device is mounted on, mechanism for detecting if no material is in the C-frame). Also, a service visit is referenced

'on page 7-23. Will all of these safety features be checked during this service visit? Who performs the services? How often are the services performed?  ;

2. Information of the prototype testing and quality assurance checks which are performed on the device to ensure the source housing is protected i from the environment (humidity, oils, etc.). Also include the maximum i temperature which source housing will be subject and clearer detail of how the source housing is protected from the environment.

3. Information on radiation surveys which are performed on each unit before it leaves IMS's facility and after it is installed at the customers facility.

4. Procedures for shipping the unit to the customer. Will each piece be shipped separately to the customer? Will the sealed source be shipped separately? The procedures must include inspection and radiation '

profiles performed on the design when it enters the U.S.A. or when received by the customer.

5. Information on who will be performing the servicing of the device (i.e.

calibrations, wipe test, maintenance, source installation, etc.).

6. Further details of the mechanism used to automatically close the shutter when the device is retracted. The details must include whether the shutter will close if the device is partially retracted.

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e i Ms. Susan J. Engelhardt- Ocwber 22, 1990  !

7. Details on why the device has a large air-gap. This gap would leave an open air-gap of 2100 m when the maximum thickness material is being measured. This large of a gap would be considered unsafe because a ,

persons extremities could be inserted into the radiation beam. '

8. Details of how and where the labels will be attached to the device. The labels must also include the model number, a unique serial number, and date of assay. -

9. Information on how condensation will be controlled inside the source housing. .

10. Information on the Heavy Metal (tungsten oxide) which is used in the i source housing design. The information must include it's physical  ;

characteristics such as it's melting point.  ;

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11. Information on the dose the worker will receive while performing the wipe test and routine maintenance on the device. On page 7-11 it states the person will receive a dose no greater than background. Is this'true ,

considering the radiation profile of the source housing?

In addition, NRC requires that all registered devices must conform to the drawings of the device submitted within the application. From reading the application, it is inferred that each device manufactured will have a different design having either different activity sources, different size air-gaps, a different number of sealed sources, or having the unit suspended instead of mounted on rails. If this is true, please call me to discuss the approach for registering the device.

We look forward to receiving the requested information. If you have any questions, please contact me at (301) 492-0689 or Steven Baggett at (301) 492-0542.

l Sincerely, O l i

John W. Lubinski l Sealed Source Safety Section l Medical, Academic, and Comercial  ;

Use Safety Branch  !

Division of Industrial and Medical Nuclear Safety, NMSS l

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Prototype testing and quality assurance checks-safety features 1.

1.1 Sprine Shutter Closing Mechanism The spring shutter closing mechanism will be checked as part of the leak test and l maintenance procedures performed every six months. The persons responsible for l performing this check are the same individuals listed in section seven (7) of the application. These individuals will receive instruction on how to perform these l tests as part of their initial training and as part of refresher training, conducted on an annual basis. Currently, the personnel performing the tests are employed by AEG, New Jersey. (Their current office is in Ft. Lauderdale, FL. and the persons conducting the training are Susan Engelhardt and John Lorenz. A copy of S. Engelhardt's resume is attached).

1.2 Air / Electric Supply Failure Detection If either, or both, the air and electric supplies should fail, the shutters will close l automatically.

Both shutters function in a ' fail-safe' manner, i.e., if the air pressure drops, the spring mechanism in each shutter body automatically closes the shutter.

If the electrical supply fails, the relay logic is designed so that the ' shutter-open' relays are immediately de-energized and the shutters close automatically. I 1.3 Mechanism for Automatically Closing the Shutters Proximity switches detect the position of the C-frame in the measuring, off-line and garage positions. The shutters can only be opened by the Operator when the C-frame is in the measuring position. As soon as the C-frame leaves the j measuring position, due either to retraction or to being knocked over, the '

measuring position proximity switch is no longer covered (and is therefore non- ,

active) and the shutters close automatically and immediately.  !

1.4 C-Frame Drive Rail System  :

An electric motor mounted on the back of the C-frame s mechanically coupled to  !

the rear wheel axle. The C-frame, fitted with three (3) wheels, two (2) at the back and one (1) at the front, traverses forwards and backwards, in and out of the measuring position on three (3)-forty-five (45) mm square steel rails. Our experience in the steel and aluminum industries over the last 35 years has shown  !

that the three-rail C-frame drive configuration provides greater stability than, say, i a four-wheel configuration.

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1.5 No-Material Detection 4

When there is no materialin the C-frame measuring gap, the measured thickness reads zero. This zero thickness value is used by tahe gauge signal processing

system as the criterion for automatically dosing the shutter. ,

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In fact, the shutters remain open for a period of approximately 10 seconds after each aluminum plate has left .the C-frame measuring gap in order for

' Standardization' to take place. Standardization is the process whereby the gauge signal processing system automatically corrects the zero thickness value when there is no material in the measuring gap. The shutters dose automatically after the 10 second standardization period.

l Zero correction, through the process of Standardization, is necessary in order to maintain the correct gauge calibration. The half-life of Caesium-137 is about 28 years which, if ignored, would result in an annual zero shift in the gauge ,

thickness reading of ca 2.3% In addition to the correction for the effect of l radioactive decay, Standardization also corrects for any possible buildup of grease of dirt on the surfaces of the radiation source windows, and ionisation detection windows, over a long period of time, i.e., months or years.

i 1.6 Service Visit  !

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The functions described in paragraphs 1.1 through 1.5 will normally be checked by the customer operating and maintenance personnel on a day to day basis. In addition, these functions will be checked by AEG personnel during their 6 month leak test / maintenance check schedule. All of the above functions need to be operating correctly in order for successful gauging to take place and therefore, i any problems with these functions would be noticed initially by the operating staff and then reported immediately to the maintenance staff.

Checking the correct operation of the above functions does not necessitate an i; individual receiving any more than normal background radiation. Any problems ';

with the above functions which could not be solved on site would be reported to AEG who would then send their engineer (s) to the site,in order to investigate i and rectify the fault (s). '

2. Protective Testing and Ouality Assurance Checks-Source Housine  !

2.1 Protection from the Environment (humidity, oil, etc) il An air blower, supplied as a standard item of equipment with the Profile Gauge, '

delivers dean air from the motor room to the C-frame at a flow rate of ca 50 cu meters / minute. The whole of the C-frame,induding the areas where the shutter housings and athe ionisation detectors are mounted, is purged continually with  ;

dean air, which prevents the ingress of oil and moisture, etc. If the air blower l

4 should fall, for any reason, an air flow detector situated in the C-frame body initiates an appropriate alarm, and also prevents further measurement from taking place until the air blower is returned to normal service.

The maximum operating temperature to which the shutter mechanisms are subjected is 70 degrees Centigrade, although they could tolerate much higher temperatures than this value. Three thermostats, located in the upright, upper and lower C-frame sections, are adjusted to a temperature of 70 degrees Centigrade.

If the C-frame purge air should fail, thus allowing the C-frame temerature to rise to 70' degrees _ Centigrade, the thermostat output (s) would cause an appropriate.

alarm to be initiated.

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This procedure is only carried out in the interests of correct thickness measurement, not to protect the equipment in the C-frame, which, as stated above, could tolerate very much higher temperatures than 70 degrees Centigrade before suffering any damage whatsoever.

3. Radiation Surveys Radiation surveys showing the radiation area around the Profile Gauge with the shutters open and closed are taken at the IMS factory during the system checkout, prior to despatch, and following installation on site. A copy of the surveys done at the installation site will be done by IMS/AEG personnel and a copy of the survey forwarded to the appropriate NRC region. Please refer to drawing 5241-III, Section 10 of our Device Registration / Specific License application.

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i The radioactive isotopes are shipped separately from the Profile Gauge and are installed in the Profile Gauge by AEG and IMS personnel on site following the main gauge installation, prior to commissioning. Radiation dose profiles are then taken as described in' paragraph 3 above.

5. Service Personnel -

AEG personnel will be performing the servicing of the device, including the calibrations, wipe tests, maintenance, etc. These personnel will have taken a 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> training course, outline included on attached pages, as well as hands on training pertinent to each of the gauge series manufactured by IMS. These persons will also take an annual refresher course,16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in length, to keep abreast of accepted practices set forth by the NRC. These training courses will be provided by Susan Engelhardt and qualified associates of hers.

6. Shutter Closure on C-Frame Retraction Proximity switches detect the position of the C-frame in the measuring, off-line 1

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and garage positions. The shutters can only be opened by the Operator when the C-frame is in the measuring position. As soon as the C-frame leaves the measuring position, due, either to retraction or to being knocked over, the proximity switch is no longer energized, and the shutters close automatically and immediately.

It should be emphasized that the shutters will close as soon as the C-frame even partially leaves the measurinst position.

7. C-Frame Measurinst Gap Aluminum strip, which is used for the production of drink cans and food container cans, amongst a large number of other products used in aircraft and other industries,is required to be produced at finished thicknesses as low as (and lower than) 10 um (0.4 mil inch) in the final cold rolling stage. The initial product starts out, however, as a hot ingot, or slab, with a thickness in excess of 10 inches, and a temperature of 450 C (840 F).

In order to be able to control the profile of the final, thin strip product, it is essential to measure and control the profile of the rolled product, whilst it is still at the thick stage.

Profile is defined as the variation of strip thickness across the full width of the strip, or slab, and is an extremely important parameter for the industry. The thinner the rolled product becomes, due to progressive reduction in the rolling process, the harder it becomes to effect the strip profile because both the lateral and longitudinal material flow are severely restricted as the strip thickness decreases.

In order, therefore, to achieve the most accurate strip profile, it is desirable to measure and control the slab profile whilst the overall slab thickness is stil in the range 1 to 10 inches. In fact, the Profile Gauge in question measures slab thickness and profile up to a maximum thickness of 250 mm (10 inches).

A characteristic of the rolling process is that when the aluminum slab thickness is still in the range 1 to 10 inches, the front end of the slab can actually ' lift up' off the roll table as it exits the rolling mill and enters the C-frame measuring gap.

It is not unknown for the front end of the slab to rise to a height of 6 feet. The momentum of the moving slab, as it approaches the C-frame,is such that the slab would simply knock over the C-frame and possibly ' carry' it some way down the mill. This would cause a great deal of damage to the C-frame and would possibly result in the gauge being out of action completely until the necessary repair work l could be carried out.

l Obviously accidents of this nature must be avoided at all costs from the point of view of both safety and cost. Safety in this context, refers only to hazards caused

by mechanical and structural damage, and not to radiological protection hazards.

If the C-frame were knocked over or displaced, the shutters would automatically dose, as described previously.

It is considered by all concerned that the distance of 2100 nun from the measuring material to the underside of the C-frame top bream, provides adequate security.

As an additional safeguard, the customer intends to install a photocell device which will detect a severely up-turned slab front-end, and, as a result, will stop the rolling mill with the slab still in it so that the C-frame can be temporarily withdrawn to its garage position before the mill is restarted.

A further reason for the large C-frame measuring gap is that with such a gap, only two radioactive sources are required to cover the whole strip width, as can be seen from the drawing 5245-01M1, Section 10 of our application. (Full strip width coverage is necessary in order to provide correct slab, wedge, profile and width measurement, i.e., the full capability of the Profile Gauge). Obviously, the smaller the measuring gap, the greater the number of radioactive sources required to cover the full strip width, and consequently, the greater the cost.

With our knowledge of the radiation dose profile around the Profile Gauge, we are able to provide the end-user with sufficient information to enable he/she to construct a suitable measuring house and protection area to confine the ratiation area around the Profile Gauge, so that no individual can receive a radiation dose rate in excess of 0.25 mrem / hour with the shutters open, in all three C-frame positions; i.e., measuring, off-line and garage (park) positions. This information is supplied with our ' Design Engineering Package' which forms part of our scope of supply for each Profile Gauge and which varies according to the customer's requirements and site layout. A copy of each individual site layout and radiological measurements will be forwarded to the appropriate NRC office for information.

8. Location of Labels Labels, induding the device model number, Profile Gauge serial number, date of assay, radioactive source serial numbers and full details of contact names and telephone numbers, etc, will be screwed to the C-frame body-Please refer to Section 10 of our application document for examples. Each of these labels will dearly show the radiation symbol and " Caution Radioactive Material". The entrance to the area where the sources are garaged will also be labelled in accordance with 10CFR20.

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9. Condensation Control An air blower, supplied as a standard item of equipment with the Profile Gauge, l delivers dean air from the motor room to the C-frame at a flow rate of ca 50 cu

i i meters / minute. The whole of the C-frame, including the area.s v/nere the shutter housings and the ionisation detectors are mounted, is purged continually with clean air, which prevents the ingress of oil and moisture, etc.

] If the air blower should fail for any reason, an air flow detector, situated in the C-frame body, initiates an. appropriate alarm, and also prevents further 1

measurement from taking place until the air blower is returned to normal service.

10. Heavy Metal Specifications -

l The characteristics of the heavy metal material used in the shutter housing j construction is as follows:

Material Tungsten (Woi4am) l Specific Gravity  : 18.9

Melting Point  : 3380 C s

1-i' 11. Received Radiation Dose During Servicing J

j All service and maintenance work on the Profile Gauge is carried out with the j source housings installed in the C-frame and with the shutters closed-please refer

to drawing 5241-111, Section 10 of our application document.

The standard method for performing a wipe test does not require that the shutters j be opened at any stage.

1 By placing the swab used for wiping the surface to be tested, on the end of a suitably long tool, and by carrying out the wipe test at arms length in the usual way, the total dose received during the wipe test operation (typical duration not more than a few seconds), will be less than background radiation dosage. j

12. Device Registration. Variation in Desia_ n As far as the Profile Gauge containing the radioactive isotope Caesium-137 is -

concerned, the quantity and activity for each Profile gauge supplied will be the same for the foreseeable future, i.e.,2 X Cs-137 Radioactive Sources per Profile Gauge with an activity of 55 Ci each. l The individual design of each Profile Gauge C-frame will vary according.to the particular rolling mill in which the gauge is to be installed. This means that there may well be diferences in the measuring position, eg, overhead suspension from a mono-rail or. supporting ground rails,' and differences in the C-frame dimensions, eg, air gap and throat depth, etc. This will always be the case because each rolling mill differs in its construction, design and product strip width. The operation of the Profile Gauge with regard to radiological protection and safety  !

will, however, remain the same for each application.

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As we discussed on the phone, a complete radiological survey of each facility will l be conducted once the sources and assembly are in place. The drawings of the  ;

facility and the radiological survey will be forwarded to the appropriate office of l the NRC.

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! I November,1990 ,

e Susan J. Engelhardt l l 1626 Fordem Ave. Madison, WI.,53704 262-8769/244-1811 T

f EDUCATION l j* 30 credits in Health Physics and Radiology at Purdue University, from 1978-1980. (Completed all coursework towards a Ph.D. In Bionucleonics). Attended Purdue as an Honors Environmental l Grant student.

Master of Science Degree, University of Wisconsin-Milwaukee,1974 to 1977. Major Zoology with a Health Physics emphasis.

.. Bachelor of Science, University of Wisconsin-Milwaukee,1968 to 1973. Major, Zoology / Biology.

. Deans List, Senior Honors -

l-EXPERIENCE j

'1982- Radiation Safety Program Supervisor / University Radiation Safety Officer

Present

Develop and implement a comprehensive Radiation Safety program for a large j

} Nuclear Regulatory Commission license to possess and use radioactive materials  !

! in medicine and research. This position includes responsibilities for nuclear j medicine, radiation therapy, all the irradiators on campus, all research endeavors that use radioactive materials or radiation as part of their activities. In addition 2- this person is responsible for all radiological safety for the Madison campus,

disposal of radbactive wastes. This person acts as the radiological emergency i 2

coordinator for the campus and acts as the University representative in contacts  ;

with the media and public/ citizen groups on matters pertaining to radiation j

protection. 'Ihis individual performs the radiation protection duties for the ,

i- Synchrotron Radiation Center in Stoughton, the UW Nuclear Reactor, and the UW l Cyclotron.-

l 1980- Senior Health Physicist at Nuclear Fuel Services, Erwin, Tennessee 1982 Responsible for 12 radiological technicians that did the day-to-day environmental sampling, safety surveys and security surveys for a nuclear fuel fabrication' facility.The person in this position was the Plant emergency coordinator for Plant operationsi and errmgecy preparedness. I .was the Union-Management Coordinator for Health and Safety. This included all fire safety, general safety, Plant inspections for radiological and criticality safety, and, wdting recommended corrective actions based on laws and Union bargaining. agreements. In this position, I acted as the Plant Criticality Safety Officer; this involved determining safe sometry for fissile class materials. I also coordinated all of the environmental p radiological sampling, both on-site and off-site. Finally, I was responsible for all  !'

of the stack monitoring and incinerator safety for the Plant site. i:

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HONORS AND SKILLS Consultant to the NRC on implementation of Part 35 and the new Part 20 Member of the EPA task force in Mixed Waste Consultant to EPA in develping air emmision standards for radioactive materials Member, Governor's Technical Advisory Committee on Low Level Radioactive Waste Lecturer to several dasses at the University of Wisconsin,1982-Present Hosted North Central Chapter Health Physics Society Meeting, fall,1988 ,

Council Mernber of the North Central Chapter Health Physics Society,1989 Council Member of the Tennessee Chapter Health Physics Society,1980 Developed the Quality Cirdes for Employee Development at Nudear Fuel Services Consultant to General Electric Company to teach courses in Ultrasound and Nudear Medicine Taught courses in Radiation Biology, Nudear Medicine, Health Physics, Physiology, and and Emergency Preparedness l Hosted the Big 10 Radiation Safety Officers Meeting 1986 Media spokesperson for the East Tennessee Chapter-Health Physics Society Advanced computer skills Excellent writing skills (see publications)

Tutor: Health Physics courses at Purdue Fellowship to attend Purdue University Research Assistant, 1975-1978, continue research at Point Beach and Kewaunce Nuclear Plants Summer Internship to do research at Argonne National Laboratory,1978 Teaching Assistant,1973-1977, taught courses in Human Anatomy and Physiology National Science Foundation Undergraduate Grant recipient 1972 to do environmental research at the Point Beach Nudcar Plant Deans List for Academic Excellence,1968-1973 PROFESSIONAL AFFILIATIONS Member of the National Health Physics Society Member of the Tennessee Chapter of the Health Physics Society Member of the Midwest Chapter of the Health Physics Society Member of the North Central Chapter of the Health Physics Society COMMITTEE MEMBERSHIPS University Radiation Safety Committee Medical Center Radiation Safety Committee Laser Safety Committee Nudear Reactor Safety Committee Governor's Technical Advisory Committee on Low Level Radioactive Waste Radioactive Drug Research Committee VA Radiation Safety Committee Consultant-Chemical Safety Conunittee Corsultant-General Safety Committee Consultant-Biomedical Waste Disposal Committee

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PUBLICATIONS Editor, contributed chapter in Biolocical Effects of Radiations, Second Edition, Daniel S. Grosh and Larry Hopwood, Academic Press, New York,1979. Chapter 11 entitled " Somatic Histiopathy" Engelhardt, Susan,1977, Radiation Biology for Nuclear Medicine Students, General Electric Company, j Nudear Medicine Course Editor, Basic Physioloey and Anatomy, Ellen Chaffee and A. Greisheimer,1974, Lippincott Press, London Boeldt, Eric, Susan Engelhardt, and Larry Veleke,1985, "An Inexpensive Method for Monitoring Effluent 1 Air from Iodination Hoods," Health Physics, Volume 49 Pergamon Press Engelhardt, Susan,1981, " Quality Cirdes in the Nudear Fuel Industry," Nuclear Fuel News, Erwin, TN Engelhardt, Susan,1981, " Radiological Emergency Plans for Nudear Fuel Facilities Producing High Enriched Fuels," Nuclear Fuels News, Erwin, TN Engelhardt, Susan,1981, " Criticality Control Plan for a Nuclear Fuel Facility that Produces High Enriched /

Highly Purified Materials.," Nudear Fuel News, Erwin, TN Engelhardt, Susan,1981,"Uses of Borates in Nuclear Safety at a High Enriched Fuel Fabrication Facility," (

Nuclear Fuel News, Erwin, TN Engelhardt, Susan and John Lorenz,1990, Radiation Safety Training Manual for Persons Installine and Maintainine Nudear Gauces, Developed for AEG/IMS of Ft. Lauderdale, FL Engelhardt, Susan,1981, " Planning to Decommission a High Enriched Fuel Fabrication Facility?" East Tennessee Chapter HPS Newsletter i

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SIGNIFICANT PRESENTATIONS "High Dose Rate Afterloaders in Radiotherapy; Advantanges and Problems," Big 10 Radiation Safety Officer's Meeting, Purdue University, W. Lafayette, IN l

" Effective Methods for Management of Low level Radioactive Waste," 1990, Big 10 Radiation J Safety Officers Meeting, Purdue University, W. Lafayette, IN

" Siting of low level Radioactive Waste Disposal Facilities," 1988, Governor's Task Force, presented to a citzens group, Two Rivers, WI

" Handling of Radioactive Waste at the University of Wisconsin," 1988, Governor's Conference for Generators of Low level Radioactive Waste, Madison, WI Panel Presentation of Handling of Mixed Waste with EPA Representatives,1988, Big 10 Radiation Safety Officer's Meeting, University of Minnesota, Minneapolis, MN

" Handling and Processing Radioactive and Mixed Waste," 1988, Big 10 Radiation Safety Officers Meeting, University of Minnesota, Minneapolis, MN

" Managing and Staffing a Radiation Safety Program with a Large Broadscope License," 1984, Big 10 Radiation Safety Officer's Meeting, University of Illinois, Urbana, IL ,

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" Effective Method for Monitoring Radioiodine Effluent from Labomtory Hoods," 1982, Big 10 l Radiation Safety Officer's Meeting, Indiana University, Bloomington, IN I

" Fire Control in a Facility Containing Large Quantities of Fissile Materials,"1981, East Tennessee Chapter of the Health Physics Society, Oak Ridge, TN 1

" Measurement of Releases from a Plutonium Facility," 1980, East Tennessee Chapter of the Health Physics Society, Oak Ridge, TN

" Effective Use of Packed Bed Scrubbers on a High Enriched Incinerator," 1980, East Tennessee Chapter of the Health Physics Society, Oak Ridge, TN

" Effects of Ultrasound on Neonatal Rats," presented at the National Health Physics Society Meeting,1977 ,

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TEACHING AND CONSULTING EXPERIENCE Consultant to the NRC on development of Part 35 and the new Part 20,1986- Present Consultant to EPA on development of air enunission standards for radioactive materials,1989-present Consultant to Promega Corporation to prepare an NRC license,1990 Consultant for IMS of England to prepare NRC licenses and device registrations in the United States,1989-present Lecturer on " Basic Radiation Protection in Laboratories," 1990, University of Wisconsin Madison, Chemistry Class Consultant,1989-present, for AEG of Pt. Lauderdale to teach " Principles of Radiation Physics and Radiation Protection" .

Lecturer on " Biological Effects of Ultrasound," 1976, wr General Electric Company Lecturer on, " Handling Radiation Emergencies," 1974-1977, General Electric Company Lecturer on " Radiation Biology for Nuclear Medicine Students," 1974-1977, General Electric Company Lab Instructor for " Cardiovascular Physiology,"1977, University of Wisconsin-Milwuakee

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Lab Instructor for " Advanced Human Physiology," 1977, University of Wisconsin-Milwaukee Lecture and Lab for " Human Anatomy and Physiology," 1974-1977, University of Wisconsin-Milwaukee NOTE: On numerous occasions I have been a spokesperson for the University regarding radiation safety matters, in the written press as well as the television and radio media.

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CONTINUING EDUCATION "High Dose Rate Afterloader Conference," University of Wisconsin Hospitals and Clinics,1990, Madison, i WI

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" International Incineration Conference," American Society of Mechanical Engineers,1989, Knoxville, .

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.' Tennessee (40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />) 1 2

" Incineration Class for Educational Institutions," at the Intemational Incineration Conference,1989, Knoxville, Tennessee, (16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />)  !

" Panel on Construction of Incinerators," at the Intemational Incineration Conference,1989, Knoxville, TN i (8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />) 1

"Part 35: How to Deal with It?," presented by the Nudear Regulatory Commission,1989, (5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />)

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" Working with and Dealing with Difficult People," 1984, Department of Employment Relations, Madison, a L WI, (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) -

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" Basic Supervisory Training," 1982, Department of Employment Relations, Madison, WI,'(48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />)

!' " Writing with Power," 1980, Nuclear Fuel Services, Erwin, TN i

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" Quality Cirdes for Employees," 1980, Nuclear Fuel Services, Erwin, Tn, (48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />)

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" Criticality Safety School," 1980, Las Alamos National laboratory, (80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />) - )

" Stack Sampling Techniques in the Nudear Fuel Cycle," 1980, SPURT, Idaho Falls, Idaho, (48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />) l

! " DOT Compliance for the Nuclear Fuel Cycle," 1980, presented by DOT, Atlanta operations, Nudear Fuel l Services, Erwin, TN, (16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />)  !

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. " Radiation Emergency Accident Care,"(REAC/1F, class, Oak Ridge Associated Universities, 1979, (40 i hours) 1, In addition'to the above, I participate in four training exercises with the Point Beach Nudear Plant and l 4

the Kewaunee Nudear Plant to test emergency response. I teach some of the coursework to the nurses and ancillary state staff who would be responding to a nudear plant accident.

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t j OTHER PROFESSIONAL ACTIVITIES '

Invited consultant to the University of Iowa, Iowa City,(1990) l 4

Invited consultant to Mayo Clinic, Rochester, MN,(1989) to evaluate incineration program e National Health Physics Meetings; attend at least every other year  ;

{ Visited Iow level Radioactive Waste Sites at Barnwell, SC, Beatty, NV, and Hanford, WA (1980)

. Invited consultant to the University of Tennessee, Knoxville, (1989) to evaluate their Positron Emission 3

- Tomography program e

} ~ Invited consultant to Indiana University Medical Center, Indianapolis, IN, (1988)

Invited consultant to Notre Dame University, Notre Dame, IN, (1988) e L

. NOTE: Unless stated otherwise, the above consults were to evaluate radiation safety programs i

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In addition to the.above, I participate in four training exercises with the Point Beach Nuclear Plant and

, the Kewaunee Nuclear Plant to test emergency response. I teach some of the coursework to the nurses and ancillary state staff who would be responding to a nudear plant accident.

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RADIATION SAFETY OFFICER COURSE FOR AEG PERSONNEL Monday,14 May,1990

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') ' 9:00-9:30 AM

Introduction:

Description of the course and what the j . goals for the course are -

9:30-10:30 AM Historical perspective and regulatory agencies i

j 10:30-10:45 AM- Break

! i 10:4511:45 AM Regulatory rationale and discussion of the morning j lectures i

11:45 AM-1:00 PM Lunch 1:00-2:00 PM Structure of the atom, binding energies, structure of I stable elements, radioactive elements, and decay of of j unstable nuclei  !

l 2:00-2:45 PM Half life and half life calculations  ;

2:45-3:00 PM Break 3:00-3:30 PM Example problems of half life and radioactive decay 3:30-4:30 PM Types of radiation: alpha, beta, gamma, X-rays, neutrons

1 Tuesday,15 May,1990

- 9:00-10:00 AM lonizing vs non-ionizing radiation, properties of the different types of radiations and how they relate to the RSO's work 10:00-10:45 AM Introduction to interactions of radiation and matter 10:45-11:00 AM Break 11:00-11:45 AM Interactions of radiation and matter-especially as it relates to gammas and Bremsstrahlung radiation 11:45 AM-1:00 PM Lunch ,

1:00-2:30 PM Interactions of radiation and matter (continued) and a demonstration of these interactions 2:30-2:45 PM B.reak 2:45-3:45 PM Rads, rems and roentgens; becquerel, gray and sieverts 3:45-4:15 PM Discussion section I

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Wednesday,16 May,1990 9:00-9:30 AM introduction to radiation biology; where our data for l

radiation effects comes from i 9:30-10:45 AM Radiation chemistry, internal vs extemal exposures to  !

radiation, radiation effects on cells genetic effects and systemic radiation effects on humans, and repair mechanisms 10:45- 11:00 AM Break 11:00-12:00 Acute radiation syndrome, delayed effects of radiation and discussion of the morning 12:00 PM-1:15 PM Lunch 1:15-2:30 PM - Means of protecting yourself from radiation; time distance and shielding (inverse square law) 1 2:30-3:15 PM Introduction to radiation dosimetry i 3:15- 3:30 PM Break 3:30-4:15 PM Introduction to calculation of dose l

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. Thursday,17 May,1990 .

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i 9:00-10:30 AM Calculations of dose continued and types of  :

dosimeters available-10:3010:45 AM Break l l

10:45-11:45 AM Types of dosimeters and discussion of the morning

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lectures 11:45 AM-1:00 PM Lunch 1:00-2:30 PM Instrumentation-description of radiation detection instruments and hands on operations 2:30-2:45 PM Break 2:45-3:15 PM instrumentation continued--check out of instruments

. before you leave to go into the field 1

3:15-4:15 PM Description of leak tests and why they are done; what to look for when doing a leak test--physical inspection as well as contamination checks l

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Friday,18 May,1990 9:00-10:00 AM Leak test procedures continued i i

10:00-10:45 AM Discussion of what has been achieved in this course -

10:45-11:00 AM Break 11:00-11:45 AM Objectives when you are leak testing a source, professionally, and from a radiation safety standpoint 11:45 AM-1:00 PM Lunch I 1:00-4:00 PM  !

Written exam and oral exam l

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