J.R. Simplot Company, Registry of Radioactive Sealed Sources … · 2019. 12. 19. · REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF"DEVICE .. (Amended in

REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE

(Amended in its entirety)

NO: CA-0305-D-J.05-S Date: April 26, 2012 Page: 1 of7

DEVICE TYPE: Slurry Analyzer

MODEL: SL Series & GS Series

MANUFACTURER/DISTRIBUTOR:

SEALED SOURCE MODEL DESIGNATION:

*H-3 (fritium) t?-LEAK TEST FREQUENCY:

PRINCIPAL USE:

CUSTOM DEVICE: DESCRIPTION:

Thermo Gamma-Metrics 10010 Mesa Rim Road

. San Diego, CA 92121 (858) 450-9811 (voice) (858) 546-1734 (fax)

Frontier Technology Corporation Model 100 Series (Cf-252)

QSA Global, Inc (Formerly AEA Technology and Arnersham Corporation) Model: CVN.CYn Series (CVN.CY6, CVN.CY7, CVN.CY8, CVN.CY14, CVN.CY15, CVN.CY16, CVN .. CY17).

FSUE State Scientific Center of Russia, Research Institute of Atomic Reactors, Division of Radionuclide Sources and Preparations, Model HK252M41 Series, ANSI/ISO Classification 97C65445.

General Electric Model GEN-Cf-100 Series Eckert and Ziegler Isotope Product La • N-252 3014 an

Total of 50 micrograms or 27 inillicuries in up to four sources (SL Series) Total of 200 micrograms or 107 millicuries in up to six sources (GS Series)

3.3 Ci (GS Series)

Six Months

General Neutron Source Applications (H)

YES NO X



NO: CA-0305-D-105-S Date:April26,2012 Page: 2 of7


Summary Description: The Thermo Gamma-Metrics Slurry Analyzers are prompt gamma neutron activation elemental analyzer designed for continuous use by the coal, cement, fertilizer, chemical and mineral industries. The different models within the SL series are identified with the designation "Model SL-76", with the 76 indicating the inlet pipe diameter (in millimeters). The GS series slurry analyzers are identified as GS-OMNI and have no pipe size designation. The input pipe diameter is typically in the range 25-50 mm.

The device consists of three major elements; (1) The Source Handling Assembly, (2) The Material Handling, Shielding & Housing Assembly, and (3) The Control Enclosure Assembly.

(1) The source handling assembly maintains correct geometry of the neutron sources with respect to detectors during normal operation. Source removal. is accomplished only through a locked access cover. Loss of power has minimal effect, since the radiation dose is essentially the same between the deployed ai1d stored positions. These positions are primarily used to minimize radiation dose to the detector electronics. The GS series has its isotopic neutron source (s) loaded into a plastic rod for insertion into the analyzer. The rod with up to six sources can be slid directly into a straight tube that passes all the way through the analyzer through either of two locked source access hatches front and back, This redundancy allows flexibility in accessing isotopic sources in mechanically tight installations. The GS series can also use an on-off electronic neutron generator which generates neutrons only when.power is applied. A flashing indicator lamp is used to indicate the ON condition whenever the neutron generator is energized. The light source has a lamp current sensor to prevent neutron generation if there is a light failure.

(2) Material Handling and Housing Assembly: Material handling is accomplished by means of standard piping which provides a flow of slurry through the analyzer thus passing the sample through a neutron field where the prompt emission of capture gamma rays occurs. The SL series uses a combination of borated paraffin and polyethylene neutron, and lead or bismuth gamma shielding to reduce radiation dose equivalent rates to less than 0.5 rem per year to any person outside the housing assembly or in the control enclosure. The housing assembly is a fiberglass structure (6 ft. 10 in. H x 6 ft. 1 in. L x 5 ft. 3 in. W) which contains all of the above subsystems and is of a rugged design for use in an outside industrial environment. Access to the radioactive sources is through a locked access door. The GS series uses lead or bismuth gamma shielding and neutron shielding consisting of physically tough chemical and UV resistant, Fiberglass Reinforced Plastic (FRP) structures that hold and contain a combination of hydrogenous sheets, borated powder and polyethylene, borated and lithiated plastic. The shielding reduces the integrated radiati~n dose equivalent rate to less than 0.1

REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EV ALUATiON OF DEVICE


NO: CA-0305-D-105-S Date: April 26, 2012 Page: 3 of7


rem/year (1 mS/year) for workers around the analyzer. The FRP structures are bolted together and to the steel analyzer frame with stainless steel fasteners to form a rigid assembly. Galvanized 1.6mm thick steel walls enclose the analyzer to further protect the shielding structures from mechanical impacts. The GS series analyzer is 6 ft. 4 in. (1936mm) high by 7ft. (2120mm) wide by 7 ft. (2116mm) long. It also incorporates a fixed built in 3 ft. (927mm) long shelf that allows a slurry flow cell to be pulled out for replacement. When running the GS analyzer with the maximum size isotopic neutron source the worst case ~adiation fields of close to 30 mrem/hr at 30cm, occur at the flow cell tunnel entrance when the flow cell has been pulled out. This operation requires less than 10 minutes and would take place 2-3 times per year yielding less than 15 mrem total dose per year to any worker intimately involved in the change out. A GS series slurry analyzer with an electronic neutron generator would be de-energized when changing out the flow cell.

(3) Associated Control Enclosure Assembly:. The associated control enclosure assembly converts the prompt gamma ray data measured by detector located opposite the neutron sources into data useful to the user. Entrance to the control enclosure is qy a locked door. The control for the GS Series with an electronic neutron generator has emergency on-off switches and lock-out switches and is placed within 1-3 meters of the analyzer.

LABELING:

The Model SL Slurry Analyzer bears the following permanent label: "CAUTION: RADIOACTIVE MATERIALS" along with a radiation symbol meeting the requirements of 10 CFR 20.1901, the label also contains the company name Thermo Gamma-Metrics as well as the isotopes and activities (including the measurement dates). The label is attached to the outside of the locked source access door (See Figure 1).

The model GS Slurry Analyzer will bear one of the Caution Radioactive materials label shown as Label 1 & 2. The label used for GS Series analyzer with Cf-252 source is shown in Label 1 and the label used for GS Series analyzer with electronic neutron source is shown in Label 2.

DIAGRAMS: See Attachments:

(1) Typical SL Installation (2) SL Orthogonal View with Features (3) GS series overview with dimensions.

REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF"DEVICE ..




(4) GS series Front view & GS series Rear view. (5) Label 1 Isotopic neutron source label & Label 2 Neutron generator source label. (6) Positions for radiation dose measurement around the GS series analyzer (7) Table 1 Radiation dose levels around the GS series analyzer for 200 µg of Cf-252 source. (8) Table 2 Radiation dose levels around the GS series analyzer for a DT neutron generator of SE+7 neutrons/second.

CONDITIONS OF NORMAL USE:

Planned Use: The Thermo Gamma-Metrics Slurry Analyzers will be used by the coal, cement, fertilizer, chemical and mine industries. The units (including radioactive sources) will be delivered by common carrier. Installation shali be perfomie<I by Thenno Gamma-Metrics personnel.

Environment: Since the units may be situated in outside industrial environments, they are designed for a wide spectrum of weather conditions ranging from snow and ice to 75 MPH wind forces. The device is capable of tolerating a temperature range of -40 to 55 degrees centigrade (-40 to 130 degrees Fahrenheit).

PROTOTYPE TESTING:

The first production SL unit was loaded with 50 micrograms of Cf-252. The assigned ANSI classification for this loading is ANSl-24-164-175-Rl. The temperature portion of this classification was derived from consideration of the materials used which were selected and fonnulated, based on manufacturers' data sheets, materials handbook values, accepted engineering practice, and experience. A fire test was not performed since the neutron shielding would not survive such a test. Most units will be loaded with less than 50 micrograms of Cf-252. The first production GS unit was tested at 38 micrograms of Californium-252 and the radiation dose extrapolated to 200 micrograms of Californium-252. The assigned ANSI classification for this loading is ANSI-34-163-163-Rl.

EXTTERNAL RADIATION LEVELS:

The manufacturer reports. that the maximum external radiation levels (measured with a Victoreen Model 459-P ionization chamber and a Nuclear Research Corp. Model NP-2 "Snoopy") when the SL device is loaded with 50 micrograms ofCalifomium-252 are:



NO: CA-0305-D-105-S Date:April26,2012


Distance (cm)

5 30 100

Radiation level (mrem/hr}

Not Tested 1.16 0.55

Page: 5 of7

Normal Loading: A Slurry Analyzer (SL) will be loaded with less than 50 micrograms of Cf-252.

The GS device maximum external radiation levels for a loading of 200 micrograms of Californium-252 are given in Table 1for30cm and lOOcm based qpon the me·asureinent points of Figure 6. The table shows radiation levels under normal operating conditions with the flow cell inserted but it also shows the radiation levels seen when a flow cell is removed during replacement. Table 2 shows the radiation dose around the GS series analyzer with a DT neutron generator of 5E+7 neutrons/sec. A Monte Carlo Transport Code (MCNP) modeling was used for this calculation. The slurry cell was assumed to be drained of slurry to provide maximum radiation dose. The slurry cell is never removed when the neutron generation for an electron•c neutron source is turned on.

QUALITY ASSURANCE AND CONTROL:

Thermo Gamma-Metrics provided a summary of the Quality Assurance Program, referencing I 0 CFR 50, Appendix B and ANSI N45.2. These procedures are outlined in the Thermo Gamma-Metrics Quality Assurance Manual to ensure quality of design material, worlananship and documentation.

Reviewer's Note: Registrant added FSUE State Scientific Center of Russia information to the sealed source model designation, Model HK252M4 l Series, ANSVISO Classification 97C65445. The QA program is unaffected.

LIMITATIONS AND/OR OTHER CONSIDERATIONS OF USE

A. The Model SL & GS Series shall be distributed only to persons specifically licensed by the NRC or Agreement States.

B. The sources contained in the devices shall be leak tested at six (6) month intervals using techniques capable of detecting 0.005 microcuries ofremovable contamination.

C. These devices shall not be subj(fcted to environmental conditions exceeding those specified in the ANSI-24-142-132-Rl classification or ANSI-34-163-163-Rl.

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REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EV ALDA TION ·oF DEVICE




D. Instructions to users: Radiological Procedures Training is provided and summarizes basic radiation safety with respect to the use of the device.

E. Installation and Relocation: This service must be performed by the manufacturer or other persons specifically licensed to perform such service by the NRC or Agreement States.

F. Emergency Procedures: As a fire could substantially compromise the shielding, specific instructions should be described and posted. Loss of neutron shielding would yield a dose rate of approximately 500 mremlhr within 1.83 meters (6 feet) of the device.

G. Source exchange shall only be performed by Thermo Gamma-Metrics or other persons specifically licensed to perform such service by the NRC or Agreement States.

H. Radioactive sources are controlled by means of a locked access panel. Keys shall be controlled by the radiation safety officer responsible for the site.

I. This registration sheet and the information contained within the references shall not be changed without the written consent of the California Department of Public Health.

J. Reviewer Note: Licensee added EZIP's sealed source models 3004, 3014 and N-252 Series· with ANSI/ISO classification of 77C66535 and General Electric Hitachi's GEN-CF-100 with ANSI/ISO Classification of 99E66524. EZIP's sealed source has a . maximum activity of 30 millicuries.

K. Emergency Procedures: As a fire could substantially compromise the shielding in the GS device, specific instructions should be described and posted. Loss of neutron shielding would yield a dose rate of approximately 143 mrem/hr within 1.83 meters (6 feet) of the device.

L. The licensee will place a sign stating, "High Radiation Area" adjacent to the analyzer when replacing the slurry cell for a GS-series analyzer using Californium neutron sources.

SAFETY ANALYSIS SUMMARY:

Based on our review of the information and test data cited below, we continue to conclude that the Model SL Series device design and Model GS series are acceptable for licensing purposes.

(

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REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION :OF DEVICE


NO: CA-0305-D-105-S Date:April26,2012 Page: 7 of7


The maximum external dose rate is less than 1.5 mrem/hr at 30 cm for Model SL series and Model GS Series in normal operation and less than 30 mremlhr at 30 cm for Model GS series when the slurry flow cell is being changed. The ANSI classifications 97C64545, 97C66545, 97C64444, 97C64444, 97C64544, 97C64444, 97C64544, 97C64444 for the QSA Global source Models CVN.CY6, CVN.CY7, CVN.CY8, CVN.CY14, CVN.CY15, CVN.CY16 and CVN.CYl 7, exceed the required classification for the intended use (43323). EZIP's sealed source models 3004, 3014 and N-252 series are classified in accordance to ANSI N43.6-1977 as C66535 and General Electric Hitachi's GEN-CF-100 is classified in accordance to 1802919-1999 as E66524. Even in the event that a fire destroys the shielding, the sources should maintain integrity. The ANSI/ISO FSUE classification for the sealed source model designation, Model HK252M41 Series, is 97C65445.

REFERENCES:

The following supporting documents for the Model SL Series and GS Series Slurry Analyzers are hereby incorporated by reference and are made a part of this registry document:

1) NBS Handbook 129, ANSI N.538, "Gauging Devices", 1979.

2) GAMMA-METRICS letters (with attachments) of February 16, 1995, April 18, 1995, and May 10, 1995.

3) Thermo Gamma Metrics letters dated February 22, 2007, March 13, 2007, April 25, 2007, and June 1, 2007, with attachments thereto.

4) Thermo Gamma Metrics letter, dated August 8, 2007.

5) Thermo Gamma Metrics letters dated February 24, 2012 and April 17, 2012.

ISSUING AGENCY: California Department of Public Health

DATE: April 26. 2012 REVIEWED BY: -~~ /:--.J> b..t,, .

Vandana Kohli

CONCURRED BY: -~~=--\-------Ro~ ~gus

DATE: April 26, 2012

REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY .EVALU:AtION OF' DEVICE ..


NQ: CA-0305-D-105-S Date: April 26, 2012 ATTACHMENT 1


SL Series

Figura 1: Typical Installation

I ! '

REGIS1RY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFBTYEVALUATIONOF-DEVICE .

(Amended in its entirety}

NO: CA-0305-D-105-S Date: April 26, 2012


SL Series

CiAM>dA SHIELD !IOI IRCH S'fORl-:1)

__ J SOURCBPA1ll

Figure 2: Orthogonal View With Features

A ITACHMENT 2

SEcnON A·/\

SECTION :S.,

I

I .I

REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES ·sA:FE'i'Y.EVALUATlo:N of' "r>EVICE


NO: CA-0305-D-105-S Date: April 26, 2012 ATTACHMENT 3


1936mm

Figure 3: GS-OJ\olNI Dimensions

Caution Radioactive Materials Label

t

I . ,

I

REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES - SAFETY EV ALUATibN OF DEVICE . .


NO: CA-0305-D-105-S Date: April 26, 2012


------. ---ATTACHMENT 4

FRONT

HATCH- FRONT DETECTOR HOUSING

:DOOR TUNNEL

DOOR-FRONT Cf SOURCE

Figure 4: GS-OMNI Front view showing the front padlocked isotopic source access hatch

BACK

HATCH- BACK DETECTOR HOUSING

HATCH - BACK TUNNEL

DOOR- BACK Cf SOURCE

Figure 5: GS-OMNI Back view showing the rear padlocked isotopic source access hatch

REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVIC~S SAFETY EVALUATION OF DEVICE



DEVICE 1YPE: Slurry Analyzer

MUrillll: G.8 mm ll1k 304 Slllldeu8t111I

Laeetengnmid Bladt on fl!llad lrdg!Dund

NosClhlnlMI

Label 1: Caution Radioactive Material for Isotope Based Analyzers

~ g !

l I I

I

r.--------.....,.---115 -----------41

IOM:TIVE MATERIAL . .

Ma1er1a1: o.a mm lhk 304 Slalnla111 Steel

La•r englllVed Blaek on 1111um1 background

No adheelva

-4 hol11111 drUI lhrougt eJ4.6 mm

Label 2: Caution Radioactive Material for Neutron Generator Based Analyzers

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REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFE1Y EVALUATION OF DEVICE .


NO: CA-0305-D-10"5-S Date: April 26, 2012 ATTACHMENT 6

DEVICE 1YPE: Slurry Analyzer

Figure 6: GS-OMNI Flux positions. Positions 7, 8, 9 and 15, 16 & 17 are symmetrically placed on the far sides.


(Amended in i~s entirety)



GS-OMNI SURVEY REPORT

DATE 2S-Mar-1 I RADIATION WORKER - R.Mut11nda DEVICE GS.OMNI

ALL VALUJ!S ARECONVERTEDID mrem/br from ,.Sv/hr and scaled from 38 µg to 200µg ofCf-252

INS1RUMEllT SERIAL NO. Used la CALIBRATION DUE

Thermo Scientific m 40 G-L 021558 ia 6-Jul-11

WENDI Amplifier: MODEL FHT642 0698 ia 6-Jul-11

WEllDI Neutron Detector: MODEL mT762 0302 6i!/ 6-Jul-11

DURING SLURRY CELL CHANGEDUf mremlhr NORMAL MODE: SLURRY CELL LOADED mrem/hr

LOC GAMMA NW1RON SUM GAMMA NEUlRON SUM

No. JOcm IOOcm JO cm IOOcm JOcm IOOcm JO cm JOOcm 30cm IOOcm JOcm JOOcm

1 0.74 0.48 0.23 0.07 0.96 0.55 0.53 0.22 0.17 0.05 0.69 0.27 2 0.52 0.38 0.18 0.07 0.71 0.45 0.84 0.27 0.21 0.16 · I.05 0.43 3 0.51 0.43 0.06 0.07 0.57 0.50 0.74 0.27 0.11 0.12 0.84 0.39 4 0.26 0 0.12 0 0.38 0 0.16 0 0.11 0 0.26 0

5 0 0 0 0 0 0 0 0 0 0 0 0

6 0.40 0 0.14 ·o 0.54 0 0.19 0 0.14 0 0.33 0 7 0.63 0.45 0.10 0.09 0.73 0.54 0.74 0.53 0.09 0.05 0.83 0.57 8 0.63 0.44 0.09 0.08 0.73 0.52 0.74 0.53 0.10 0.05 0.84 0.57 9 0.68 0.42 0.07 0.10 0.75 0.52 0.63 0.53 0.06 0.06 0.69 0.59 10 3.37 1.47 9.68 3.79 13.05 5.26 0.23 0.11 0.05 0.03 0.28 0.14 11 6.68 2.11 21.05 6.05 27.74 8.16 0.13 0.11 0.07 0.07 0.20 0.17 12 2.89 1.68 2.21 2.21 5.11 3.89 0.38 0.15 0.08 0.07 0.46 0.22 13 0.74 0 .0.58 0 1.32 0 0.53 0 0.47 0 1.00 0 14 0.63 0 0.39 0 1.03 0 0.53 0 0.32 0 0.84 0 15 3.32 2.00 2.11 3.68 5.42 5.68 0.29 0.18 0.12 0.11 0.42 0.29 16 7.37 2.11 ·20.53 4.74 27.89 6.84 0.41 0.18 0.11 0.11 0.52 0.29 17 1.84 1.11 1.84 2.32 3.68 3.42 0.23 0.13 0.05 0.03 0.28 0.16

Table 1: The radiation flux around the GS series analyzer with a maximum content of 200 micrograms of Californium-252.

REOISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFE'IY"EVALUATION"OF DEVICE


NO: CA-0305-D-105-S Date: April 26, 2012 AITACHMENT 8


GS-OMNI

Modeled values are in mremlhr from a 5E+o7 n/sec DT nGen. Values are 0 when the neutron generator is OFF.

INSTRUMl!NT SERIAL NO.

GS-OMNI MCNP MODEL MCNPV5.4

OPllRA TING MODE mrem/hr

LOC GAMMA NEU1RON SUM No. 30cm lDOem 30cm lOOcm 30cm IOOcm

1 0.07 0.03 0.11 0.05 0.18 0.09 2 0.10 0.04 0.15 0.07 0.25 0.11. 3 0.10 0.04 0.24 0.09 0.34 0.14 4 0.12 0.07 0.85 0.64 0.97 0.71 ..

5 0.27 0.11 4.06 1.56 4.33 1.67 6 0.13 0.07 0.82 0.63 0.95 0.70 7 0.10 0.04 0.24 0.09 0.34 0.14 8 0.10 0.04 0.16 0.07 0.25 0.11 9 0.07 0.03 0.12 0.06 0.19 0.09 10 0.11 0.06 0.28 0.26 0.39 0.32 11 0.22 0.09 2.04 0.77 2.26 0.85 12 0.28 0.13 2.95 2.05 3.23 2.17 13 0.17 0.08 1.78 1.08 1.95 1.16 14 0.16 0.08 1.90 1.09 2.06 1.17 15 0.28 0.13 2.73 2.01 3.01 2.13 16 0.22 0.08 2.07· 0.78 2.29 0.86 17 0.11 0.06 0.29 0.28 0.40 0.33

Table 2: The radiation flux around the GS series analyzer with a DT neutron generator of 5E+7n/sec. When the analyzer is inoperative the neutron generator is turned off. During slurry cell change-out or other maintenance the neutron generator can be locked-out.

Documents

J.R. Simplot Company, Registry of Radioactive Sealed Sources … · 2019. 12. 19. · REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF"DEVICE .. (Amended in