ML20127E493

Application for Renewal of License SNM-1826,authorizing Use of 240 G Pu:Be & 300 G U-235.Revised Procedures RS-SOP-880.1,RS-SOP-880.2 & RS-SOP-880.0 Also Encl.Fee Paid

ML20127E493
Person / Time
Site:	07002872
Issue date:	05/30/1983
From:	Palko G REUTER-STOKES, INC.
To:	NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
Shared Package
ML20127E198	List: ML20127E194 ML20127E199 ML20127E205 ML20127E216 ML20127E236 ML20127E277 ML20127E288 ML20127E299 ML20127E385 ML20127E493 ML20127E522 ML20127E539
References
22365, NUDOCS 8505200100
Download: ML20127E493 (37)

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Radioisotopes Licensing Branch C0%"fss

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Washington, D.C. 20555 N

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Subject:

Renewal of Special Nuclear Material License SNM-1826 Issued to Reuter-Stokes, Inc.

Gentlemen: '

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Reuter-Stokes, Inc. requests that our Special Nuclear Material license, SNM-1826, be renewed in accordance with 10 CFR 70.33(b). The following information is

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submitted in accordance with 10 CFR 70.22. We have followed Reg. Guide 10.3 in a-1 preparing this application.

y 1.0 The full name of the applicant and the principal offices and plant location f

are:

If Reuter-Stokes, Inc.

i 18530 South Miles Parkway J;

Cleveland, Ohio 44128 5

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-ir 1.1 Reuter-Stokes, Inc. is a Delaware corporation. The principal investors in I

-4 Reuter-Stokes, Inc. are Quidnet Company, MorAmerica Capital Corporation,

-a Narragansett Capital Corporation, along with several private individual p

investors which include key members of management. There is no control i

exercised over Reuter-Stokes, Inc. by any foreign corporation or foreign 2

-i government, nor is there any known control over any of its officers or employees; however,14.2% of the voting stock of the company is held by Canadian citizens. Principal officers of Reuter-Stokes, Inc. are:

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Robert A. Kempe, President

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RECEIVED BY 1.FMB Hudson, Ohio 44236 i

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George Palko, Vice Presig(rtt(8pdths

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reuter $ stokes 18530 South Mdes Parkway Cleveland, Ohio 44128 Radioisotopes Licensing Branch May 30,1983 Division of Fuel Cycle and Material Safety Page 2 Thomas B. Fleming, Vice President, Marketing 7755 Holyoke Drive Hudson, Ohio 44236 Citizenship: U.S.

Frank W. Zalar, Treasurer 7625 White Pine Ct.

E Mentor, Ohio 44060 g

Citizenship: U.S.

John C. Kroon, Vice President, Research & Development 7745 Clarion Drive Chagrin Falls, Ohio 44022 Citizenship: Canadian 2.0 Reuter-Stokes, Inc. has only one operating plant in the U.S., that listed in Section 1.0.

All licensed materials will be used or processed at that location.

The special nuclear materials will be used for two specific applications described in 2.1 and 2.2 below.

2.1 The U-235, U-234/U-235 combination, or U-238 is electroplated out of solution onto electrodes which are then assembled into fission counter / chambers. Geometry and application of fission counters / chambers varies greatly, from in-core reactor measurements of neutron activity, to counters / chambers used for research studies. Attachments 1 through 5 give a good representative sample of the different fission counters / chambers to be manufactured by Reuter-Stokes, Inc.

2.2 Sealed sources containing PuBe will be used to test the performance of neutron radiation detectors which we manufacture for agencies of the U.S.

Government and for private industry. The sources are kept either in our standard neutron flux box, a four foot paraffin-lined cube into which the detectors to be tested are placed, or the sources are kept in polyethylene containers of sufficient size to moderate the fast neutrons, which are then placed near the detector to be tested.

3.0 This license is requested for the following nuclear material:

a)

Plutonium, 240 grams maximum as sealed sources (PeBe).

b)

Plutonium, 300 micrograms, any form.

c)

U-235,300 grams of contained U-235, either as metallic or oxide form, as purchased from D.O.E., Isotope Sales, Oak Ridge, Tennessee, or from a private supplier. A typical isotopic analysis is as followst

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18530 South Miles Parkway

- Cleveland, Ohio 44128 Radioisotopes 1.icensing Branch -

May 30,1983 Division of Fuel Cycle and Material Safety Page 3 Isotope Wgt.1%

U-234

.96 U-235 93.12 U-236

.45 U-238 5.47 No other metallic contaminants exceed 100 ppm.

d)

U-234/U-235 combined, 9 grams, in combination by percentage typically 80% U-234 and 20% U-235, in metallic or oxide form, with a typical isotopic content as follows:

Isotope Wgt.1%

U-234 79.93 I

U-235 20.00 U-236 0.07

.U-238 0.07 e)

U-235, one gram as sealed sources.

f)

U-233,250 micrograms, as metallic or oxide form' as purchased from D.O.E. or from a private supplier.

4.0 The following individuals will use or directly supervise the use of special nuclear material:

_ George Palko Vice President Operations / Radiation Safety Officer l

Fred Glesius -

Physicist Clark Gerber Chemist

- Arthur 3. Stokes Assistant to the President Jan E. Orbin Nuclear Test Engineer C. Hubbard Ford Nuclear Test Supervisor / Assistant Radiation Safe-ty Officer John Zilka

~ Physicist I

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'18530 South Miles Parkway Cleveland, Ohio 44128 Radioisotopes Licensing Branch May 30,1983

.. Division of Fuel Cycle and Material Safety Page 4 4.1 Name

. George Palko

- Education 1975 John Carroll University - B.A. Degree (Completed several courses in nuclear physics which included theory in radioactive lsotopes)

Attended numerous conferences and semim 4 related to radioactive materials.

Work Experience Employed at Reuter-Stokes, Inc. from 1959 to the present... Served 'as

. Manager of Operations from 1967 and as Vice President of Operations since 1977.

Received 23 years of on-the-job training at Reuter-Stokes in the following categories:

a) Principles and practices of radiation protection.

b) ' Radioactivity ' measurement standardization 'and monitoring techniques and instruments.

c) Mathematics and calculations basic to the use and measurement of -

radioactivity.'-

d) Biological effects of radiation.-

Experience during this time included working with all radioactive materials listed in License No. 34-18156-01 for the duration of their usage with this Company.

Trained and has worked under the direct supervision of J. Myers, formerly a

-General Manager employed at Reuter-Stokes, and A.3. Stokes, currently an Assistant to the President of the Company.

Served as the Radiation Safety Officer for Reuter-Stokes for the past 15 years.

4.2 Name

. Fred Glesius Education 1970 Cleveland State University - B.S. (Physics) 1972 Cleveland State University - M.S. (Physics)

.While at Cleveland State, took Radiation Laboratory for 33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br />, I quarter, and worked with-the following sealed sources of less than one mil!! curie:

' Americium 241, Bismuth 207, Iron 55, and Cadmium 109. Worked (n; der the r'

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f-reuter Q stokes 1

18530 South Miles Parkway Cleveland, Ohio 44128 Radioisotopes Licensing Branch May 30,1983 Division of Fuel Cycle and Material Safety Page5 supervision of qualified individuals who taught the principles and practices of radiation protection on the job.

Included in other physics courses taken were radioactivity measurements, monitoring techniques, and instruments, including mathematics and calculations for radioactivity measurement.

Approximately one year (1969) was spent working at Cleveland State University in the laboratory of Dr. Karl Casper, Nuclear Physicist, doing research on a Rock Coal Monitor using the sources previously mentioned.

Work Experience Employed at Reuter-Stokes, Inc. from 1970 to the present time as a Physicist.

Further on-the-job training was received at Reuter-Stokes in the handling of radioactive materials such as Americium 241, Iron 55, Cadmium 105, Cobalt 60, and Uranium 235, as well as three neutron sources - Americium Beryllium, Plutonium Beryllium, and Radium Beryllium.

These sealed sources were used in the testing of detectors and in the design of instrumentation.

Involved in experimental work at the University of Missouri, Ohio State and the State University of New York at Buffalo nuclear reactor facilities.

4.3 Name Clark Gerber Education 1963 Ohio University - A.B. (Chemistry)

Work Experience Employed as a Radio-Chemist at Reuter-Stokes from 1963 to the present.

Used more than 150 grams of Uranium 235 to plate fission counters each year. Since 1979, has used more than 200 milligrams of Uranium 234 each year to coat neutron counters.

For three months in 1967, several trace sources to test counters were made from 3 millicuries of Cobalt 57. Over a period of several years, Strontium 90, in liquid form, was fabricated into detectors, as a check source. These detectors were used as calibration instruments.

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Ituter [ stokes

--18530 South Mdes Parkway.

. Cleveland. Ohio 44128 Radioisotopes Licensing Branch.

May 30,1983 c-

' Division of Fuel Cycle and Material Safety Page 6 For a period of two months in 1976, stainless steel plates were coated using approximately-30 grams of Neptunium 232 converted from a powder to.a liquid Neptunium Nitrate).

These plates were part of a high energy threshold neutron detector in a hodoscope.

Training was received on-the-job at Reuter-Stokes in the principles and practices of radiation protection, radioactivity measurements, monitoring techniques, instrumentation, mathematics, and calculations basic to the use

. and measurement of radioactivity.

4.4 Name

~ Arthur 1 Stokes.

Education -

1 1940 Kent State University - B.S. (Chemistry)

'1940 - 1942.

Two years of graduate work in University of Delaware Organic Chemistry Work Experience l

Founded Reuter-Stokes, Inc., with F.

Reuter, in-1956 to _ design, manufacture, and test detectors. Presently Assistant to the President of Reuter-Stokes. In 1956, purchased a Radiuni Beryllium 10 millicur'e source -

for testing neutron detectors.. During 1956 - 1957, purchased.51 millicuries -

of Radium which were used for Geiger tube testing and for measuring the gamma' response of neutron detectors.

In 1960, started plating-fission

. counters with Uranium 235. An 8 curie Cobalt source was purchased to test

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compensated and uncompensated ion chambers.- Set up a 5 curie Plutonium -

Beryllium source in 1969 to test not only compensated and uncompensated -

lon chambers, but also all neutron detectors and Bf-3 counters.. From 1960 through 1967, purchased _the following' sources for spectra testing Beryllium window proportional counters:

Cadmium 109 - 1 millicurie Bismuth 210 (Disc.) - 0.0237 microcuries Iron 55 (Disc.)- 10 microcuries Cobalt 57 - 10 microcuries

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During 1968 and 1969, was involved in a special research project to develop

- a Beryllium detector. For this project, a 250 millicurie source of Antimony

124. was purchased. frorn A.E.C.L. of Canada. Upon completion of this

- project, the source was returned.

Since 1969, has been involved in other acquisitions (since disbanded) and now the majority of time is devoted to research and development.

s reuter ", stokes 18530 South Miles Parkway Cleveland, Ohio 44128 Radioisotopes Licensing Branch May 30,1983 Division of Fuel Cycle and Material Safety Page 7 Has received on-the-job training and experience in the principles and practices of radiation -

protection, measurement, monitoring, instrumentation, mathematics and calculation.

4.5 Name Jan E. Orbin Education 1966 - 1970 Kent State University - Took courses toward a B.S. degree in Physics (completed Physics, Mathematics, and Chemistry courses) 1977 Cuyahoga County Community College - Completed 21 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br /> of Electronic Data Processing courses.

1978 - 1981 Cleveland State University > B.S. (Physics)

While a student at Kent State University, completed a Nuclear Physics course from January to March, 1969, handling the following sealed sources of less than ' a millicurie (trace sources)in conjunction with the course:

Cobalt 57 (1/2 curie)

Iron 57 Rhenium 186 Cobalt 60 Indium 116 Rhodium 104 Worked under the supervisica of qualified individuals giving on-the-job training covering the principles and practices of.

radiation protection, including radioactivity measurement standards, monitoring techniques, and instrumentation, mathematics, and calculations for measuring radioactivity.

- Work Experience Employed at Harshaw Chemical Company, a Kewanee Industry, from April, 1973, through September,1974, as a Senior Research and Developmental Technician. While taking TLD measurements and while working in the Solid State Dector Division with basically Ge(Li) detectors, which were Lithium drifted Germanium detectors, the following sealed trace sources were used:

Carbon 14 Americium 241 Cobalt 60 Cesium 137 Iron 55 u

N 118530 South Miles Parkway Cleveland, Ohio 44128 Radioisotopes Licensing Branch.

'May 30,1983 -

Division of Fuel Cycle and Material Safety Page 8 -

Worked' under qualified supervision and received on-the-job instructions on radiation protection, including techniques -in measuring and monitoring instrumentation for radioactivity..

Employed at Reuter-Stokes, Inc. from October,1974, to the present as.a Nuclear Test Engineer.

Performed measurements and tests on detectors using 4 Plutonium-Beryllium sources (one 5 curie, one 2.5 curie, one.8 curie )

and one 0.22 curie)- Cobalt 60, etc., and received on-the-job training in the -

handling of radioactive materials.

Performed high level gamma tests (activation) on_. compensated ion chambers and reactor life tests on BF-3 counters at the Cornell University Ward Nuclear. Reactor Laboratory using Cesium 137 and Cobalt 60 as follows:

Cesium 137 (located at the Radiation Biology Laboratory), source strength of 768.72 curies as of January 1,1973.

Cobalt.60, measured content of 11,650 curies as of September 26, 1962.

Tests were performed during a 7-year period for a total of approximately 60 -

days.

Worked with qualified reactor personnel and received on-the-job instructions during this time.-

Performed Activation testing, Reactor Life testing, and Flux testing in the 2 megawatt reactors at the State University at Buffalo Nuclear Science and Technology Facility. Performed gamma sensitivity testing using the -Van de Graaff accelerator, which gave roughly 1 x 10" R/hr., l.5 mey using a gold target.

Tests were performed during a 1-year period for approximately 10 days in.

the Nuclear Reactor Laboratory at Ohio State University using their 10 kilowatt research reactor for neutron sensitivity testing of in-core probes.

Tests were performed during a 4-year period for approximately 10 days in the Research Reactor facility at-the University of Missouri at Columbia using their 5 -megawatt reactor for neutron testing of in-core and out-of-core detectors.

Tests were performed during a 4-year period for ten days at the Argonne

~ National Laboratories using the high-level gamma source in the Chemistry Building with a Cobalt 60,100,000 curie source.

Supervised the installation of I curie of Americium 241 in Reuter-Stokes Instruments' RSS-811 systems at customer facilities.

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t reuter [ stokes 18530 South Miles Parkway Cleveland, Ohio 44128 -

Radioisotopes Licensing Branch -

May 30,1983 Division of Fuel Cycle and Material Safety Page 9 4.6 Name C. Hubbard Ford Education 1949 Parsons College - B.S. (Physics) 1955 State University of Iowa - M.S. (Physics)

Work Experience.

Employed as Nuclear Engineer and Section Head of the Detector Group at the Convair Corporation from 1955 to 1961 working on fast neutron dosimeters for nuclear powered aircraft. The following sealed sources were used for calibration and standardization:

Plutonium-Beryllium - 5 and 10 curies Polonium-Beryllium

.5 curie Cobalt - I curie -

Employed as a Nuclear Engineer at NASA - Lewis from 1961 to 1973.

Worked on a safety instrument (detector) which was used to monitor the radiation inside the perimeter of the reactor containment room (a 1 curie Cobalt source). Performed spectroscopy research putting the Americium-Beryllium source (50 curies) in various spheres of material in air and water to rneasure the neutron spectra which came through the material (source used approximately While at NASA was a licensed reactor operator, having complete knowledge of the principles and practices of radiation protection, monitoring techniques -and instruments, radioactivity measurement standards, and mathematics and calculations used to measure radioactivity and the biological effects of radiation.

Involved in the design of a Zero Power Reactor No. 2 (Uranyl Floride Reactor) for research as a possible back up in nuclear rockets in space.

Employed at Reuter-Stokes, Inc. from 1974 to 1978 as a Nuclear Engineer in the development of radiological gas filled detectors for industrial and research applications. Served as Nuclear Test Supervisor at Reuter-Stokes from 1978 with responsibility for the safe use and handling of test sources, which include up to 10 curies of. Cobalt, and 7.5 curies of Plutonium-Beryllium.

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Cleveland, Ohio 44128 Radioisotopes Licensing Branch May 30,1983

. Division of Fuel Cycle and Material Safety Page 10 '

4.7 - Name John Zilka Education 1973 Ohio State University - B.S. (Physics) 1973 - 1974 Faculte des Sciences, Paris, France - Five courses in Thermodynamics and Waves 1977 Cleveland State University - M.S. (Physics) - Special studies in Solid State While at Ohio State University, performed 3 experiments using a sodium lodide detector as part of the curriculum.

Work Experience From August,1977, to September,1980, employed at Victoreen Instruments.

Was the-Senior Physicist from August, 1977, until February, 1980, responsible for calculating the sensitivities of radiation monitoring systems, taking into consideration the type of radiation, heat flow, and electronic parameters. Served as Project Manager of small special nuclear detection monitors. Served as Product Specialist in Marketing from March,1980, until-September, - 1980. - Received formal on-the-job training relating to the principles and practices of radiation protection consisting of the proper handling. of isotopes as -well as protective equipment and instruments.

Conducted training courses relating to the operation and use of radiation monitoring instrumentation for Victoreen and the Peoples Service Electric and Gas Salem II nuclear power plant employees. Performed the following isotopic effluent calibrations traceable to the National Bureau of Standards:

Isotope Amount Isotope Amount I-131 1 uCi Kr-85

.5_Ci Xe-133 2 mci Ba-133 100 uCi Cs-137 100 uCi Co-60 100 uCi Employed at Gould, Inc. as a Staff Engineer in the Test and Evaluation Department working on advanced capability torpedo from September,1980

.until 1982.

Employed at Reuter-Stokes, Inc. from 1982 to the present as a Staff / Physicist.

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18530 South Mdes Parkway

' Cleveland. Ohio 44128_-

l Radioisotopes Licensing Branch May 30,' 1983 Division of Fuel Cycle and Material Safety Page 11 s

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5.0. Figures 1'and 2 are floor plans of the radioactive materials plating lab and the ele.ctronic test lab. Figures 3,4 and 5 describe the type of fume hoods used in the plating area. Both are of Reuter-Stokes design with sufficient air flow, minimum of 120 feet /second in the working area.. Waste material'

' which is radioactive is disposed of into 35/55 gallon steel drums which are then disposed of as described-in Section_9.0. No radioactive material-is

? disposed of into the city sewer system. Air monitoring of vents used in the plating lab has shown no detectable alpha / gamma contamination when usin'g a Union Industrial Equipment (Fall River, MA) and Mine Safety Appliances'.

(Pittsburg, PA) air samplers,- and the counting equipment described in i

Section 6.3.

Based upon these measurements, we have concluded that no measurable quantities of radioactive material have been vented to.the-atmosphere.1

-5.1 For uranium materials received in~ granular form, the shipping container is used for storage. When dissolved into solution, the liquid is stored in non-breakable containers. Less than 100 grams of uranium will be in solution t

form at any one time. All uranium is stored in the plating' lab area, with most of the uranium stored in a security container, under the close -

supervision of our chemist (See Figure 1).'

I 5.2 The PuBe sources are stored either in a paraffin-lined test box measuring 4 feet cubed, lined with six inches of paraffin,' or polyethylene containers of

.I sufficient size-to moderate fast neutrons. Smaller sources are stored in proportionally smaller containers.

5.3 Laboratory areas are protected agains't unauthorized access during 'non-working hours by A.D.T. Protection Services. Fire protection is provided for by fire extinguishers as located in Figures 1 and 2, by fire safety instructions.

- from the Reuter-Stokes Safety Committee, by the Warrensville Heights Fire Department, which has been_ alerted to the fact that the building at 18530 South Miles Parkway contains radioactive material, and which has a floor plan showing the internal storage locations of the radioactive material. A more comprehensive description is presented in Attachment -10, RS-SOP--

880.0,' Reuter-Stokes, Inc. Physical Security Plan and Procedure for the Protection of Special Nuclear Material of Low Strategic Significance.

6.0 Reuter-Stokes Inc., will maintain an adequate number and selection of radiation detection instruments as required by the operations being performed.

It is the responsibility of the Radiation Safety Officer to l

maintain the proper calibrated radiation detection instrumentation.

6.1 - All Reuter-Stokes radiation detection survey instruments will be calibrated at intervals not-to exceed 180 days and after each time the instrument is serviced.' Survey instruments will be calibrated by RAD Services, Inc., of J

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18530 South Miles Park,way Cleveland, Ohio 44128 Radioisotopes Licensing Branch May 30,1983 Division of Fuel Cycle and Material Safety Page 12 Laurel, Maryland, or other vendors at the discretion of the Radiation Safety Officer. Survey instruments will not be calibrated at Reuter-Stokes, but a check of each instrument prior to use will be made to determine that the instrument is working properly.

6.2 Survey instruments now in use by Reuter-Stokes are:

1 Nuclear Chicago, Model 2588, B-y,1-2500 mR 2 Victoreen, Model 491, B-y, 0.1-100 mR 1 Victoreen, Model 490, a-B-y, 0.05-20 mR 1 Victoreen, Model 490, a,0.05-20 mR 6.3 Other Laboratory Counting Equipment and Monitoring Instruments:

6.3.1 Bicron 3 x 3 NaI (TI) well detector in a 2 inch lead shield. Associated electronics are as follows:

1 Ortec Model 113 Preamp 1 Ortec Model 485 Amplifier 1 Canberra Model 1436 Single Channel Analyzer 1 Ortec Model 719 Timer 1 Ortec Model 775 Counter 1 Ortec Model 446 High Voltage Power Supply 8

The system gamma sensitivity is 3.0 x 10 cpm /mg of U-235. This system is used for the quantitative determination of uranium disposition in the plating process. It is also used to measure wipe tests of work areas during periods of peak activity of the uranium plating process. It is also used to evaluate the wipes taken off those sources which are required to be wipe tested periodically. The system is calibrated prior to use with a relative standard of 5 milligrams of U-235 developed at Reuter-Stokes using volumetric and mass measurements and equipment with a total error factor of + 5% The calibration for the evaluation of wipe tests is described in Attiichment 7, RS-SOP-880.2, Procedure for Wipe Testing Alpha Emitters. The system is capable of being interfaced with a multichannel analyzer which can then identify unknown gamma radiation.

6.3.2 A 2II geometry flow counter using P-10 gas which is of Reuter-Stokes design and construction. The system sensitivity is 0.5 counts / disintegration. for alpha radiation. System electronics are as follows:

1 Ortec Model PC 109 Preamp or equivalent 1 Ortec Model 115 Power Supply 1 Ortec Model 410 Amplifier 2 Ortec Model 431 Timer / Scalers 1 Power Designs Model 2K20 Power Supply or equivalent

reuter $ stokes 18530 South Mdes Parkway Cleveland. Ohio 44128 Radioisotopes Licensing Branch May 30,1983 Division of Fuel Cycle and Material Safety Page 13 This system is used for evaluating the wipe testing of sources, air sample counting, and swab test wipe testing of laboratory work areas. The system is calibrated prior to each use using an Am 241 alpha reference source, New England Nuclear Model 300, containing 0.00751 microcuries and an activity level of 1.67 x 10" dpm. The calibration method is described in Attachment 7, RS-SOP-880.2, Procedure for Wipe Testing Alpha Emitters.

6.3.3 Reuter-Stokes Model RS-C4-1606-203 gamma lon chamber, Serial No. P-3561, with a sensitivity of 1.25 x 10-" A/Rhr established by N.B.S. on 1 74. This is used as a primary standard for gamma measurements.

6.3.4 Various neutron counters are manufactured by Reuter-Stokes which can be used as survey instruments. These counters are calibrated prior to use in a neutron flux box which is calibrated by the gold foil activation method to be 642 NV + 10% when a 5 curie PuBe source is used. The calibration was

~

performed in May,1983 and is traceable to N.B.S.

6.4 The persons who are authorized to perform calibrations, or have them performed under their strict supervision are:

George Palko, Radiation Safety Officer Jan Orbin, Test Technician Clark Gerber, Chemist Hub Ford, Nuclear Test Supervisor, Assitant' Radiation Safety Officer The pertinent experience of these individuals is presented in Section 4.0.

7.0 Reuter-Stokes has a policy and program for assuring as low as reasonably achievable occupational radiation exposure. NRC Regulatory Guide 8.10 entitled " Operating Philosophies for Maintaining Occupational Radiation Exposures as Low as Reasonably Achievable" calls for the documentation of Management's commitment to the regulatory requirements of Part 20 of Title 10 of the Code of Federal Regulations. This policy contained herein is prepared, distributed, and supported in response to the above Guides and Regulations, it is hereby stated that it is the policy of the management of Reuter-Stokes, Inc. to conduct all operational activities involving utilization of radioactive materials in such a manner that as low as reasonably achievable (ALARA) occupational radiation exposure will be assured. The discussion which follows describes the manner in which this management commitment outlined above is administered.

7.1 Reuter-Stokes, Inc. has established a Radiation Safety Committee to assist the Radiation Safety Officer in achieving ALARA commitments. The Reuter-Stokes Radiation Safety Committee consists of the following members:

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'18530 South Miles Parkway Cleveland, Ohio 44128 -

. Radioisotopes Licensing Branch May 30,1983 Division of Fuel Cycle and Material Safety Page 14

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RADIATION SAFETY COMMITTEE:

George Palko Gabriel Fortin Phil Marotta -

Laura Lastafka Fred Glesius Melissa Patterson Clark Gerber Jan Orbin Hub Ford John Zilka Additions and deletions of members will be at the RSO's discretion.

7.2 It is the responsibility of the Radiation Safety Committee to see that surveillance programs and investigations are conducted to insure that.

occupational exposures are as far below the specified limits as reasonably achievable.

The Radiation Safety Committee will meet at least quarterly. Minutes of the Radiation Safety Committee meetings will be documented and distributed to all applicable persons within the Reuter-Stokes Organization.

Special meetings of the Radiation Safety. Committee may be scheduled as required for the discussion of items requiring timely consideration or for special topics that cannot be handled at a regular meeting.

The

- distribution of-information developed and/or scrutinized at committee meetings will be made to all personnel and all policies and standards will be implemented by the Committee members carrying out their individual duties and responsibilities.

7.3 The following items are examples of the functions that are performed by the Committee and its members for assuring ALARA exposures. It is not intended in any way to limit the scope of functions to be performed by the Committee.

(1). Review of Procedures (2). Review of Exposure Sources (3)

Review of Abnormal Exposures (4)

Review of Training (5)

Review of Job Preplanning (6) - Review of Job Results It'is the responsibility of Reuter-Stokes, Inc. to inform each individual employee of his/her responsibility to operate in a manner which keeps occupational exposures ALARA.

L5

- ~ muterEstokes 18530 South Miles Parkway Cleveland, Ohio 44128 Radioisotopes Licensing Branch May 30,1983 Division of Fuel Cycle and Material Safety

. Page 15 7.4 The overall responsibility for the safe use of special nuclear materials has been assigned to the individual designated Radiation Safety Officer (RSO),

' George Palko, Vice-President of Operations.

This individual has the authority to control any and/or all operations in the interest of radiological safety and compliance with the provisions of existing Regulations and Guidelines.. The Radiation Safety Officer or another individual designated by him that is qualified by training and experience will be responsible for the following duties:

a.

Handle all contact with Federal, State, and Local Regulator Agencies relative to the licensing and use of radioactive materials either directly or through his designated representative.

b.

Control the procurement, use, storage, transfer, and disposal of all radioactive materials, including documentation.

c.

Maintain adequate radiation survey instruments and see that each instrument is calibrated every six months and after each instrument servicing, and used properly for radiation surveys as needed.

d.

Establish a routine and an emergency radiological safety survey program.

e.

Establish and conduct the " Radiation Safety Training Program" and maintain up-to-date " Instruction to Reuter-Stokes Personnel" (See Attachments).

f.

Supervise the leak testing of all sealed radioisotope sources on a 6 month basis, or as necessary to determine that operations are being conducted within safe limits and according to license requirements.

g.

Notify appropriate regulatory agencies promptly of any accidents involving radioactive materieI< and provide reports as required.

. h.

. Maintain an adequate supply of radiological safety equipment and enforce use as required.

1.

Establish and maintain a medical control program for personnel which may_ include pre-placement, annual and termination physical examinations.

-J.

Assume control and institute corrective action in - emergency situations. In the event of an emergency involving special nuclear material, the Radiation Safety Officer must assume full responsibility for:

(1) _ Developing effective radiation emergency plans to:

Promptly and accurately evaluate any unusual incident.

See that personnel receive immediate medical attention.

Limit the extent of radioactive contamination.

Manage all necessary accident repair and recovery operations.

Institute remedial action to prevent reoccurrence.

(2)

Instructing all radiation personnel in what action they must take in an emergency.

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18530 South Miles Parkway Cleveland Ohio 44128 Radioisotopes Licensing Branch May 30,1983 Division of Fuel Cycle and Material Safety Page 16 (3)

Providing ample emergency equipment, instruments, and protective devices.

.(4)

Knowing who to contact for medical, fire, and police assistance.

(5)

Documenting the facts concerning the incident.

(6)

Preparing the prescribed reports to regulatory agencies; management, and insurance carriers as required.

k.'

Supervise the personnel monitoring program, including issuance of dosimeters and maintenance - (.! necessary records and reports.

Review exposure reports from film badge service monthly.

7.5 The following suppliers will furnish dosimetry and bioassay services as indicated. Reuter-Stokes is not committed to the following suppliers and reserves the right to change such vendors at the Radiation Safety Officer's discretion:

FILM BADGE SUPPLIER Siemens Gammasonics, Inc.

Health Physics Services Box 1367, Oakton Street Station Des Plaines, Illinois 60018 DOSIMETER PENCIL SUPPLIER Victoreen Instrument Division 10101 Woodland Avenue Cleveland, Ohio 44101 BIOASSAY SUPPLIERS Eberline Services Division P.O. Box 75126 Chicago, Illinois 60675 Helgeson Nuclear Services 5587 Sunol Boulevard Pleasanton, California The film badge service monitors for penetrating and non-penetrating X-ray, gamma and beta doses, and for fast neutrons.

Exposure reports are evaluated monthly and include dose accumulation to the skin and whole body.

Monthly, quarterly, and year-to-date accumulated doses are provided. Notification level to the Radiation Safety Officer is 0.40 rem.

At the discretion of the RSO, pencil type dosimeters are used occasionally when only a gamma dose is to be measured.

i Y

YO 18530 South Miles Parkway Cleveland. Ohio 44128

~

Radioisotopes Licensing Bianch May 30,1983 Division of Fuel Cycle and Material Safety Page 17 The Bioassay service provides for a monthly urinalysis for those people actively engaged in electroplating radioactive material. A whole body

~

. count by Helgeson Nuclear Services will be taken whenever their service is available in our area.

8.0 Reuter-Stokes, Inc. has established a radiation safety training program for employees who independently carry out operations involving the utilization of radioactive materials. No employee will be assigned such duties until judged competent to do so.

The safety training program will consist of three phases:

a.

Initial Training b.

On-The-Job Training

. c.

Periodic Training The inital training / orientation program will consist of basic radiological safety education applicable to the operations performed at Reuter-Stokes, Inc. Subjects covered will include (but not be limited to):

a..

Reuter-Stokes' policy concerning Safety and Reuter-Stokes' radiation protection program.

b.

Related fundamentals of basic radiation physics, such as:

1.

Fundamentals of nuclear physics.

2.

Methods of contro!!ing radiation exposure while utilizing radioactive materials cont'ained within industrial gauging devices.

3.

Mathematics basic to the use and measurement of radiation sources.

4.

Biological effects of radiation.

c.-

Use of personnel monitoring equipment.

d.

' Radiation detection instrumentation.

e.

Regulations and guidelines applicable to Reuter-Stokes' operations involving utilization of special nuclear materials.

-f.

Radiation safety operating procedures.

I The on-the-job training program will consist of:

a.

Reviewing the use of personnel monitoring devices.

b.

Reviewing the use of radiation detection instrumentation..

.c.

Evaluation of packaged radioactive materials practices and procedures.

d. -

Proper storage of special nuclear materials at Reuter-Stokes' facility..

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reuter ' stokes 18530 South Miles Parkway Cleveland, Ohio 44128 Radioisotopes Licensing Branch May 30,1983 Division of Fuel Cycle and Material Safety Page 18 A periodic radiation safety training program will be conducted annually and will consist of reviewing:

a.

Radiation safety practices and procedures.

b.

Changes or ammendments to Reuter-Stokes' licenses.

c.

Nuclear Regulatory Commission regulations.

d.

Practices and procedures for receiving radioactive materials.

e.

Changes in routine or emergency procedures.

f.

Use of radiation instrumentation.

g.

Use and practices relating to personnel monitoring devices.

h.

Radiation form and reports required by licensing procedures and current regulations.

Should circumstances warrant, the contents of the training programs listed above may be modified to meet existing needs deemed appropriate to protect health and to minimize danger to life or property.

The documentation of periodic or refresher training provided, except for on-the-job, will be maintained. However, such documentation will not be maintained for a period longer then two years.

The Radiation Safety Officer will be responsible for establishing the radiation safety training programs. The training will be conducted by the Radiation Safety Officer or qualified persons designated by the Radiation Safety Officer.

9.0 Wastes generated as a result of the uranium plating process will be reduced to a solid state and stored in a 35/35 gallon drum. Contaminated wipes, tools, gloves and other materials used in the wipe testing of sources shall also be stored in the drum. When full, the drum will be forwarded to one of U.S. Ecology's locations in Beatty, NV or Richland, WA for disposal.

Alternate disposal sites, such as Chem-Nuclear System, Inc., Barnwell, South Carolina, may be substituted by the RSO after determination that the facility is a properly licensed disposal site. Sealed sources containing plutonium shall be returned to the original manufacturer for disposal.

NOTE:

In December, 1980, the Congress enacted the Low-Level Radioactive Waste Policy Act of 1983, transferring from the federal government to the states the responsibility to dispose of commercial low-level radioactive waste (LLRW).

The Act permits the states two options: each state may act unilaterally to dispose within its own borders of LLRW generated by institutions and industries in that state; or, the states may join together in interstate compacts to manage and dispose of these wastes on a regional basis.

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18530 South Miles Parkway Cleveland, Ohio 44128 Radioisotopes Licensing Branch May 30,1983 Division of Fuel Cycle and Material Safety Page 19 The Act further provides that after January 1,1986, a state

. acting' unilaterally or a regional compact (E.G., the Northwest Compact, Rocky Mountain Compact, Southeast Interstate Compact) may exclude from their disposal facilities the LLRW generated outside their states.

The state of Ohio is an eligible state in the Midwest Interstate Compact on Low-Level Radioactive Waste along with 12 other states.

They are Kentucky, Michigan, Indiana, Illinois, Wisconsin, Kansas, Missouri, Iowa, Nebraska, Minnesota, South Dakota and North Dakota.

Due to rapidly rising disposal costs and declining volume allocations at the three existing disposal sites, Ohio's radioactive waste generators may be faced with storage and disposal problems. Thus, a midwest regional low-level waste burial site needs to be developed as rapidly as possible.

Reuter-Stokes is a member of the Ohio Radioactive Materiais Users Group (ORMUG). The radioactive material users of Ohio support the concept that adequate LLRW disposal facilities become available in this region. This will permit services and activities using radioactive materials to continue to operate for the benefit of Ohio's people. In the meantime also, to minimize'-

insofar as possible the needed disposal facility, volume reduction processes and measures will be encouraged among radioactive material users.

These processes include crystallization, dehydration, compaction and incineration.-

Ohio's General Assembly will be asked soon to adopt the ~

Midwest Interstate Low-Level Radioactive Waste Compact.

This compact will provide the cooperative effort among the eligible states and the facilities for proper low-level radioactive waste management in the region, while also protecting the safety and health of those living in the region.

10.0 Reuter-Stokes has posted in both laboratory areas, and storage areas, a copy of emergency procedures to be used in case of emergency. The procedures outline the immediate action to be taken to prevent the release of radioactive material or further contamination of personnel and non-restricted work areas. Copies of these emergency procedures are sub-mitted in Attachments 8 and 9.

1

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18530 South Miles Parkway Cleveland, Ohio 44128 Radioisotopes I.lcensing Branch May 30,1983 Division of Fuel Cycle and Material Safety Page 20 11.0 A leak test will be performed on all plutonium-beryllium and other alpha-emitting sealed sources every quarter according to.RS-SOP-880.2, Procedure for Wipe Testing Alpha Emitters, (See Attachment 7). Only those persons designated in Section 6.4 will be authorized to perform the

- leak testing, or to have it done under their strict supervision. Test samples will be taken from the source or from appropriate accessible surfaces of the device in which the source is mounted or stored. Records of these leak

- tests will be kept and made available for inspection by authorized agencies.

Any leaking sources will be immediately withdrawn from use, and the emergency procedures outlined in Attachments 8 and 9 will go into effect.

' Repair or disposal provisions will be performed under the responsibility of the Radiation Safety Officer.

12.0 The Radiation Safety Officer will be responsible for the proper keeping of records. These will include, but are not limited to:

a.

Review and approval of Purchase Orders for Radioactive Material.

b.

' Review of wipe test data and surveys.

c.

Review of personnel exposure records.

d.

Receipt of and survey of incoming radioactive material.

e.

Review and check of inventory of radioactive material.

f.

- Check that shipments of radioactive material are made only to authorized recipients.

13.0. Surveys of gamma radiation levels in work areas containing special nuclear materials will be performed quarterly under the supervision of the Radiation Safety Officer or an individual listed in Section 6.4, as designated by the R.S.O. The surveys will be performed at the same period as the wipe testing / leak testing, and will include a survey for alpha levels in the radioactive materials plating lab. Figures 1 and 2 show recent surveys of gamma and alpha radiation levels in restricted work areas.

In addition to quarterly surveys, all personnel working in the radioactive materials plating lab will be surveyed for alpha contamination prior to leaving the area for breaks, lunch, or end of shift. Protective clothing, hands, top and bottom of shoes, and other areas which could become con-taminated, will be surveyed.

Sincerely, REUTER-STOKES, INC.

re Vice President, Operations GP/mg u

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1 REUTER-$ TOKES, INC.

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1191 cm

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6.35 cm dia.

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MHV jack y.

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63.24 cm2 g.

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0.25 kg

' TYPICAL INTEGRAL PULSE HEIGHT SPECTRUM MATERIAL 4-

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1100 Aluminum Windows.

1100 Alumirnm Connector.

Brass, silver plaed Insulation-Detector.

Alumina ceramic

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12 pf t

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MAXIMUM RATINGS Voltage.

1000 volts

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150 C

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Type HN Net weight..

0.8 kg MATEP.lAL Outer shellandinner electrodes.

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Magnesium Insulation-Detector.

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Alumina ceramic Neutron sensitive material..

Uranium enriched 93% in U-235 Total Quantity of U-235.

1.6 gms Fill gas.

76 cm Hg - Argan/ Nitrogen CAPACITANCE.

140 pf RESISTANCE @ 25* C.

.10'2 ohms (minimum) l MAXIMUM RATINGS i

Voltage.

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300 0 spEGRAL BIAS CURVE

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0.7 cps /nv *20%

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to 108 nv Voltage range...

300 to 800 Volts Output pulse characteristics (average) 8*

Charge output..

7 X 10 " coulombs Collection time.

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Operation, as specified here,is greatly de-

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Concentric cylinders with uranium coatings 4

~Ie provide the neutron sensitive area. Aluminum alloy g

is used in construction to minimize neutron ab-sorption and residual activity. All seats are directly r

bonded ceramic to metal. insulators are high-purity alumina ceramic and are desig ned to assure stable, long-term noise-free operation of the chambers even at elevated temperature.

(29 45 A.

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Specifications

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MECHANCAL Maximum dianeter...

8.02 cm Maximum overallit;sath...

33.18 cm Connectors.

Type HN Net weight.

2.4 kg MATERIAL Outer shelland Inner electrodes...

. 1100 Aluminum Connector.

6061 Aluminum Insulation: Detector.

. Aluminaceramic

~

1 Connector.

Alb.mina ceramic Neutron sersitive material.

Uranium enriched >93% ;s U-235 Total quantity U-235 = 1.3 gm CAPACITANCE (See Note 1)

Signalelectrode to shell.

150 pf HV electrode to shell..

250 pf RESISTANCE @ 25' C Signalelectrode to shell.

10'8 ohms (minimum)

HV electrode to shell.

10'2 ohms (minimum) c

'INTE AL BIAS CURVE MAXIMUM RATINGS

~

Interelectrode voltage.

1000 Volts a

Temperature.

300 C l

Bum-up life:

for 10% decreasein sensitivity.

3 x 102o nyt(thermal)

TYPICAL OPERATING CHARACTERISTICS (See Note 2) g AC thermal neutron sensitivity..

>1 x 10-'v/nv DC thermal neutron sensitivity..

>1.2 x 10-'8 amp /nv

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0.7 cps /nv

" j7 AC gamma sensitivity.

< 1 x 10-'Y/R/hr DC gamma sensitivity..

< 5 x 10-" amp /R/hr i

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>4.5 R/hr/nv DC alpha current.

< 8 x 104 amp AC alpha and noise component.

104 nv equivalent Voltage range..

400 to 700 volts Thermalneutron flux range in counting mode.

to 108 ny in MSV mode.

>104 to 10'onv a

NOTE 1: With other electrode grounded.

NOTE 2 Operating characteristics are greatly dependent on electronics.

All data presented here is based on measurement using a wide band preamplifier such as the model PA-5 manufactured by b

General Atomic.

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__ f RS-06-0201-231 inCoreF uxProbe w

3 for use in your WESTINGHOUSE PWR I'

f Complete with Right Hand or Left Hand Drive Cable L.

Combining the detector with the helical drive cable which exactly mates with your specific movable drive system, Reuter-Stokes offers the complete assembly ready for use.

In 1968, the RS-C6-0201-231 was developed by Reuter-Stokes for the flux mapping systems of

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Westinghouse-built reactors. It incorporates 14

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years of in-core detector experience into an as-

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7-i sembly specifically designed to traverse the multi

...i path system smoothly, with accurate output signa!

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and long detector lifetime. It is manufactured and

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tested to rigid OC requirements for commercial

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'i power reactors. Specific design and manufacturing i ;. ;,

features include:

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1. Excellent insulation resistance at temperature l

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,q providing minimal signal leakage and permit-A i

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~.:. "-.

.',.i ting use over a wide flux / temperature range.

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2. Separate sealing of detector assembly and cable assembly to eliminate signal variation at (0302) 3

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. E'h; temperature from gas expansion-migration.

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3. Design details and proprietary methods of pro-

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cessing to insure high leakage resistance ovar (OAn).

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4. Carefully matched, machined and bonded com-f.1.:

e. gi ponents to minimize the possibility of detector

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failure resulting from insertion and withdrawal.

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Follow ng is a partial listing of operating re-jag ff1$

D actors where Reuter-Stokes in-core probes are k

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i

.. t. Wh..f Connecticut Yankee Point Beach 1,2 g. w.e

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D.C. Cook 1 Prairie Island 1,2 W

H. B. Robinson 2 Robert E.Ginna

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4 ik-i Joseph M.Farley 1 San Onofre 1

[ f.).;3@$'g

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h Jose Cabrera 1 Surry 1,2

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44 North Anna 1,2 Zion 1,2

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Specifications MECHANICAL Maximum chamber diameter.

0.478 cm Drive cable diameter.

0.478 cm

~

Chamberlength..

5.56 cm Drive cable length.

53.3 meters g

l Connector.

Amphenol #27 7 MATERIAL TYPICAL SATURATION CHARACTERIS. TICS i

Chamber Outer shell.

304 Stainless steel Inner electrodes.

304 Stainless steel

- '~

Insulation.

Alumina ceramic Detector Cable

.f Outer sheath.

Inconel600 l

Center conductor.

Inconel600

~

Insulation.

Al 03 2

Drive cable Helix, lay wires, coil.

Carbon steel (Note 1) l Neutron sensitive material

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Description.

Uranium enriched 93% in U-235 Total quantity U-235.

0.4 mg

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MAXIMUM RATINGS Voltage between electrodes.

200 Volts

-[

Temperature.

375 C Thermal neutron flux.

2 X 10" ny Burrtup life.

n for 10% decreasein sensitivity.

3 X 102o yt p.

IMPEDANCE Resistance @ 25 C.

> 5 X 10'2 ohms 375 C.

>10s hms l

o Capacitance Detector plus cable (Std. Lyth.).

16,000 pf l

TYPICAL OPERATING CHARACTERISTICS l.

Voltage.

.100 Volts

/...

l Thermal neutron flux range.

. To 1 X 10" ny l

Thermal neutron sensitivity l

(perturbed)(Note 2).

.1.5 X 10-" amp /nv 20%

Gamma sensitrvity.

.1.2 X 10-" amp /R/hr 2 20%

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NOTE 1: User must specify whether his system requires right or left hand drive.

NOTE 2: Before shipment sensitivity of each detector is calibrated in a pool-type test reactor with etfective cross section of 500 bams M

A L@o m U S. A 4M4/79

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4 sg A tachment 5

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Engineering Data Sheet 9.14 s.

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nn RS-06-1100-21X Regenerative o

Loca Power f

1 Range Monitor (LPRM) Assembly

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Compatibility L

-;f The Reuter-Stokes RS-C6-1100-21X regenerative LPRM is t

k mechanically and electrically compatible with the General r,

Electric design BWR. No modifications are required to any

'3 computer programs, including gain adjustment factors and

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end-of-life prediction. The assembly, including fission

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chambers.TI P calibration tube, plunger, seal plug, and gland, y

i is made in a series of sizes to meet the exact dimensional requirements for direct replacement in the core support

%R structure of all BWR designs. Designs used in every BWR

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reactor, including those with variations such as lower vent 4

S holes plugged. LEMO connectors, flow stop washer, special j

i features for BWR5, etc., are completely familiar to Reuter-1 3

i Stokes. All of our LPRM units have been installed using established removal and replacement procedures and i

f standard calibration procedures. As of June,1981, over g

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f' ifQ 100 Assemblies have been installed with no problem

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of interchangeability 522p

Background

jQA$i Reuter-Stokes has over 20 years' experience in the design,

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and manufacture of miniature fission chambers of the types I

dQM used in the LPRM Assembly. Combining the in-core

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experience of our Cleveland and Canadian plants, we have

~j 7 Q-supplied in-core detectors to 64 operating commercial w-mpfi,@h hf ; '

reactors, as of June,1981-more than any other j

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manufacturer.

The RS-C6-1100-21X regenerative LPRM design is y";.,74 S.;

i9 based on that background. Welding and ceramic-to-metal F-J '

bonding are state-of-the-art. Critical design considerations such as the detector / detector lead cable seal receive

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particular care, in engineering and in manufacturing Q,;

control.The entire LPRM design has been tested

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J thoroughly in actual commercial operation.

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N' Conformance

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Design, materials, manufacturing processes and examina-l

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tions of our LPRM Assembly conform to the rules of the ASME Boiler and Pressure Vesse: Code. All of our LPhM l

s units meet the requirements for C!as 1 E Safety Related Nuclear Instrumentation. Reuter-Stosu s manufactures i

LPR M Assemblies to a Quality Assurance program in

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accordance with the requirements of U.S. code 10CFR50, c

l Appendix B, and related codes of other nations.

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h Alumineceramic Neutron sensitibmetorial Detector / Cable.

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i insulator (each end)

'(*U+mU) isolabon seal i

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5 Outer shell Inner electrodes MineraHnsulated i

.Joaxialcohle.

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A Fission chambers: RS-06-1100-21X regenerative LPRM Four miniature fission chambers are used in each LPRM Gamma sensitivity.

2 x 10 amp /R/hr Assembly Each chamber is approximately 6.4 cm long, and Burn-up life.

. 8.4 yrs @ 6.7 x 10'3 is attached to a hermetically-sealed. mineral-insulated n/cm2s ' in a BWR spectrum (note 3) signal cable which extends beyond the reactor vessel ELECTRICAL DESIGN boundary The fission chambers and cable are designed for exposure to the reactor coolant; the sheaths of the signal Design operating voltage.

.100 Vdc cables are brazed into the seal plug. which is a part of the Maximum operating voltage.

. 200 Vdc reactor pressure boundary All materials are in conformance Insulation resist'nce(IRMincludes cable) >10'2 ohms. 250C with the required codes for in-core safety reiated equipment.

>107 ohms 300 C Following are specifications for each detector:

Initial calibratiC. _ Jrrent.

~500uA M ATE RI ALS THERMAL DESIGN Outer shell.

. 304L stainless steei Maximum design temperature (continuous).

.289'C Inner eiectrodes.

. Titanium NOTES:

Insu!ation.

High-punty AI,02

1. Flux iml in test reactor is determ:ned by activation foils.

Neutron sensitive material Measured senFivity of miniature fission chambers is greater (23'U 235U during operation).

2U and 2asU in the test reactor because the effective thermal neutron NUCLEAR DESIGN cross-section is greater.

Neutron sensitivity.

.0 88 x 10-" amp /n/cm s-'

2. Gamma-induced currents in the signal cable are in test reactor (note 1) substanhally lower than those for the detector, and do not 0.5 x 10-" amp /n/cm2s-'

affect the knearity of the detector.

in BWR spectrum

3. Burn-up life corresponds to a reduction in neutron Thermal neutron flux range.

.1.4 x 10'2 to 1.4 x 10

sensitivity to the point where neutron-to-gamrna signal ratio n/cm2s

is calculated to be 5:1. Extension of hfetime is possible Deviation of neutron signal from through user expenence, including gamma flux and linearity at nominal voltage.

. 1%(note 2) electronics calibration.

MineraHnsulated cable: RS-06-1100-21X regenerative LPRM Mineral-insulated coaxial cables are used to Insulation, cable.

. High-purity Al;O3 carry signal currents from the miniature connector.

. Rexolite fission chambers through the reactor

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pressure boundary to the instrumentation WPEDANCE connecting cables At the connector end.

Resistance @ 25 C

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the coaxial signal cable termination is (includes fission chamber).

. >10'2 ohms protected by a moisture-resistant coating (w/o connector) on the insulator. The connector mates with Resistance

• 300^C existing LPRM connecting cables for full

( ncludes fission chamber).

. > 10' ohms interchangeability between LPRM assem-I bhes of varying manufacture. Problems with (w/o connector) this seemingly routine connection generally Cable Capacitance.

~ 300 pf/ meter account for more LPRM detectors being in Mineral-insulated cables used in the bypass than any other single cause, includ_

ing seal failure Reuter-Stokes provides RS-C6-1100-21X regenerative LPRM meet detailed connection and waterproofing or exceed all maximum ratings for the l

instructions with each LPRM Assembly to Assembly as a whole, including lifetime, reduce connection time and provide secure, maximum temperature, maximum pressure, watertight connections.

and maximum radiation levels. The gamma-induced current in the cables is negligible.

M AT ERI ALS and will not affect kneanty Outer sheath.

. 304 L stainless steel

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inner conductor.

. 304L stainless steel twn~ensms

I Operating characteristics (actual)of RS-C61100-21X regenerative LPRM Reactor Power 100*e

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50 100 150 200 250 Volts Burn-up data (actual) of RS-C6-1100-21X regenerative LPRM Vjpw3*"MW7m mM?TT"n*WTM"g gLg4;gw g gga{g MWTP?"FQ8vCW'"?%q.mm The information shown here illustrates qmaguegghggg;%g g

data on the RS-C6-1100-21X regenerative LPRM. taken from operating commercial Q.

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reactors The plateau curve :above' is

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,p mq,)yg, p gg, that of the RS-C6-1100-21X in a BWR ji' j

j spectrum. with the reactor at 100i power hg *....

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Nominal operau ng witage is 100 Vdc 4

with a corresponding signal output of d *IHb l

.l. M s b b /l l ~~!.".*M"'"' Z' [

le %

',h 500uA The miniature fission chambers D}.

1 used in the RS-C6-1100-21X mgenerative

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LPRM will withstand a bias voltage of ff i

d 200 volts withou t breandown

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_g The burn-up cun es at nghi compare

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LJ

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_L 1 ij the characteristics of a conventiona: fis-

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sion chamber with thoseof a regenerative chamber both devices operating in the

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k.c same reactor The curve for the regenera-M~ e-b!' l - -- l -

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~[.i' I. b b ' b L[i b*,

trve device is essentially flat. because

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1 the *U in the fissionable coat;ng is t*

e f-

%.QEQQ @pg g ggg { gyt,1,g y g.h converted to *U under neutron bom-bardment. replacing the "U that is being y,

consurred The curve reflects data col-e5enP7 a

kg M EN:mwWemmemw&wvwwwm e"d#ACA*NMn"'CCMMUSy lected to date on the RS-C6-1100-21X regenerative LPRM operating in a com-Li*

mercial power reactor When the *ll is 3

b - d.-

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d b J J [ - -. b T 1,* p )

b i

totally converted. the curve of the regen-

[d

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. *b erative device will drop. following the

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'l f lPl'-l d _ [ 1 h!5)l []e j typical curve of a conventional device

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..g until end-of-life Projected burn-up of j p- - ( - g ~ l*]* <l g*'. - *d"M. " J '{.,ij

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life for the regenerative L PRM is 8 4 years.

U

, ha in a total fluence of 17 6 x 10" n cm2 gj.p-l l l= u l I -. ~i N w l e I i.

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! ~ l "li.,pg a.

a a

% MNi: Li l' T L ~'~ L! E. L _ l-l:

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g...... y p

O M f(lll' VE Li' M!Clf f I qIf 'y j;1!.q l

e.

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l Curve of regenerative LPRMial and

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%),

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standard LPRM(tn both in operation 1

in the same commercial reactor in l

b.*h.. !MLlPRMTMK1#tBRM4REMEMVTE& M* M oy n y n m, n m n n n n n n. m. m

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RS-06-1100-21X regenerative LPRM l

l Engineered for specific BWR design Protective cover (sealed, watertight) l b

b L ]A I 1 O

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Detector A Detector B

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Detector C Detector output connectors Detector D f$

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II C

0 0-6 5

s T.I.P. tube Housing material....................................... 304 stainless steel i

Maximum temperature.................................. 289o C, continuous Maximum pressure................................. 1250 psig, continuous Individual units are constructed to interchange exactly with devices in General Electric Company BWR designs. Variations tuch as lower vent holes plugged, LEMO connectors, flow-stop washers. special BWR5 features, etc. are allowed for in individual designs.

18530 South Miles Parkway I

Oeveland, Ohio 44128. U.S. A Phone (216) 581-9400

• Telex 985253 r,.m w.nusA noo - su r -au