ML20138N128

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Registry of Radioactive Sealed Sources & Devices,Safety Evaluation of Device Gamma Gauge for Model SAM1. Certificate:NR-8080-D-801-B
ML20138N128
Person / Time
Issue date: 02/10/1997
From: Steven Baggett, John Lubinski
NRC
To:
Shared Package
ML20138N051 List:
References
SSD, NUDOCS 9702270155
Download: ML20138N128 (14)


Text

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REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE HQ 1 NR-8080-D-801-B DATE! February 10, 1997 PAGE 1 OF B DEVICE TYPEr Gamma Gauge MODEL:

SAM 1 i

& MUFACTIIRPR/DISTRTRUTORr Process Technology, Inc.

1122 Calumet Avenue Calumet, MI 49913 SEALPD SOURCE MODEL DESIGNATION!

Amersham Models: AMC.D2 AMCL l

ISOTOPE; MAYTMUM ACTIVITY!

Americium-241 1.0 millicurie (41 MBq)

LFAK TEST FRFOUENCY; 6 Months PRTNCTPAL USE!

(D) Gamma Gauge CUSTOM DEVICE!

YES Y

NO 9702270155 970219 PDR RC SSD PDR

RE(JSTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE

]

M0 1 NR-8080-D-801-B D&221 February 10, 1997 PACE 2 OF B DEVICE TYPE:

Gamma Gauge i

DESCRIPTION:

The Model SAM 1, Slurry Ash Monitor, is a fixed device located in a coal preparation plant.

The device serves the same purpose as a through the belt analyzer, but rather than being installed on a coal conveyor belt, the coal is passed through the device in slurry form via a closed-loop piping system.

The device i

determines the ash and solids content of one or more slurry streams.

The device is contained in a cabinet, which under normal operating conditions is locked preventing access to the source block.

The Model SAM 1 consist of a one millicurie americium-241 sealed l

source in a 9 in. x 9 in. x 8 in. (23 cm x 23 cm x 20 cm) polyethylene source block.

The device provides a through-the-pipe signal and can provide a signal for iron correction by use of back scatter detection.

When the device measures back scatter, source model AMCL will be used.

Whereas, when it doesn't measure back scatter, source model AMC.D2 will be used.

In this case, the hole for the back scatter detector will be capped.

The source is tightly pressed into the polyethylene source holder and securely locked in place with three set screws.

The source holder is then press fitted into a hole that is bored to the exact dimension of the source holder in the source block.

The remaining parts of the source block are then assembled.

The i

source block is sealed with a silicone based sealer and then is l

bolted together.

Six bolts securely hold the block together and two of the bolts, in opposite corners, have holes drilled through the tail-end of the bolts and a padlock is placed behind the nuts after the nuts are secured.

When the source block is sealed and bolted, the source is inaccessible.

The source block would have to be disassembled in order to have access to the source.

The source and detector (s) are all located within the source block.

The coal slurry passes through a two inch diameter channel in the block.

The source and detector are located on opposite sides of the channel with the back scatter detector on the same side with the source.

The source is totally shielded by the polyethylene and the radiation beam through the two inch channel is not accessible at any time.

The device does not incorporate a shutter mechanism.

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

EL.L NR-8080-D-801-B D&211 February 10, 1997 PAGE 3 OF S DEVICE TYPE:

Gamma Gauge l

DESCRIPTION (con't):

i The system has been equipped with a seepage detector consisting of two electrodes placed in the space between the source and the channel.

If this space fills with water, the electrical i

connection will be complete and the analyzer will shut itself i

down notifying the operator that there is a crack in the source l

block, and immediate servings is required.

1 The slurry is moved through 1/4 in. (0.64 cm) thick, 2 in. (5 cm) diameter steel piping.

The steel piping does not extend through L

the source block.

It is attached to the top and bottom of the source block with flanges.

Each flange is attached to the source block by four bolts.

The source block is housed in a steel cabinet which has dimensions of 36 in. x 72 in. x 43 in. (92 cm x 183 cm x 109 cm).

Process Technology, Inc.

no longer sells, distributes, or services any of the devices.

LABELING:

For persons generally licensed, the source block is labeled in accordance with Section 32.51, 10 CFR Part 32.

The labelling consist of two labels.

The first label (see (a) of attachment 3) contains the radiation symbol, isotope, activity, date of assay, device model number and serial number, name of manufacturer (Process Technologies, Inc.), and the words " RADIATION HAZARD".

The second label (see (b) of attachment 3) contains all the appropriate warnings and instructions required by 10 CFR Part 32.

Both labels were manufactured from aluminum with a yellow background and magenta or purple writing.

Each is attached by four screws to the source block.

For persons specifically licensed, the source block is labeled only with the first label (see (a) of attachment 3).

An additional label is attached to the front door of the cabinet which contains the source holder.

This label will contain the i

name of the manufacturer (Process Technologies, Inc.), date of assay, isotope, the words " CAUTION RADIOACTIVE MATERIAL", and "THIS DEVICE MAY CONTAIN RADIOACTIVE MATERIAL IN THE SOURCE BLOCK

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1 REGISTRY OF RADIOACTIVE SEALED SOUPCES AND DEVICES SAFETY EVALUATION OF DEVICE l

i MQ.1 NR-8080-D-801-B DATEL February 10, 1997 PAGE 4 OF S t

i l

DEVICE TYPE:

Gamma Gauge l

1 i.

f TARRT.TNG (con 8t):

1 SAM 1 AND CAN BE POSSESSED UNDER AN APPROPRIATE LICENSE".

The i

label was manufactured from aluminum with a yellow background and

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magenta or purple writing.

8 DIAGRAMS:

l See attachments 1-3.

i i

l CONDITIONS OF NORMAL USE:

A The device is intended for use in a coal preparation plant.

The 3

source block is located inside a locked steel cabinet.

Operating i

temperatures may vary from 32*F to 104*F (0*C to 4 0*C).

The

[

i device will withstand humidity up to 100% RH.

Vibration, shock, j

and corrosion will be typical of those associated with t

environments in the coal industry.

i PROTOTYPE TESTING:

l 4

i The sealed sources which may be contained in the device have 1

j achieved the following ANSI N542-1977 classifications:

Model ANSI N542-1977 AMC.D2 77C64545 j

AMCL 77C64344 Several prototype units of the SLM1 have been in use at coal preparation plants since 1989.

None of these devices have experienced problems with leakage nor have any ever experienced r

radiological accidents that resulted in radiation exposures.

]

j EXTERNAL RADIATION LEVELS:

Process Technology, Inc. reports that the radiation levels from the device are 0.1 area /hr (1 MSv/hr) at 2 in. (5 cm) from the source block and that the levels measured at lengths beyond 2 in.

are not discernable from background.

Since the device is located l

inside a cabinet which under normal circumstances is locked, the source block is not accessible and the dose rates outside the cabinet will not be above background.

In addition, the dose rate on the face of the sealed source is i

5.7 mram/hr (57 pSv/hr).

l i

i 1

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REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE HQ.1 NR-8080-D-801-B DATE: February 10, 1997 PAGE 5 OF B DEVTOE TYPEt Gamma Gauge OUALTTY ASSURANCE AND CONTROL:

Process Technology, Inc. had submitted a quality assurance and control program which governs the production and distribution of this device.

The program had been deemed acceptable for licensing purposes by NRC.

]

LTMTTATTONS AND/OR OTHER CONSIDERATTONS OF USE!

  • The device may be used by specific or general licensees of the NRC or an Agreement State.
  • Handling, storage, use, transfer, and disposal:

To be l

determined by the licensing authority or as required by Section 31.5, 10 CFR Part 31 or Agreement State equivalent.

  • The user may perform certain maintenance on the device (see the device operation manual).
  • The device shall be installed and initially tested for safety warning components, labels, external radiation levels and leak tested by Process Technology, Inc. or other persons specifically licensed by the NRC or an Agreement State.
  • The device shall be leak tested at intervals not to exceed 6 months using techniques capable of detecting 0.005 microcurie (185 Bq) of removable contamination.
  • This registration sheet and the information contained within the references shall not be changed without the written consent of the NRC.

1

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REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES j

SAFETY EVALUATION OF DEVICE EL.1 NR-8080-D-801-B DEEE1 February 10, 1997 PAGE 6 OF S DEVICE TYPE:

Gamma Gauge i

j BAFETY AMALYSIS SIEGEARY:

The sealed source, maximum activity of 1 millicurie, is totally l

shielded by the polyethylene.

In addition, the channel that the i

slurry flows through is encased by the polyethylene and the l

radiation beam through the two inch channel is not accessible at any time.

The source block is located inside a cabinet which is locked under normal circumstances.

Only when maintenance is to be performed is the cabinet to be unlocked.

In the event of a fire or damage to the source block, the user will be instructed to notify the manufacturer for repair or disposal.

The sealed sources models AMC.D2 and AMCL have achieved ANSI

-N542-1977 classifications of 77C64545 and 77C64344 respectively.

This indicates that temperature, pressure, impact, vibration, and puncture stresses imposed during use are highly unlikely to cause i

breach of containment integrity of the capsule.

During use the j

source is sealed within the' housing such that the source is protected against possible airborne corrosive and other types of contaminates.

Process Technology, Inc. has submitted sufficient information to provide reasonable assurance that:

  • The device can be safely operated by persons not having training in radiological protection.
  • Under ordinary conditions of handling, storage, and use of the device, the byproduct material contained in the device will not be released or inadvertently removed from the source housing, and it is unlikely that any person will receive in any period of one calendar year a dose in excess of 10 percent of the limits specified in the table in Section 20.1201(a), 10 CFR Part 20.
  • Under accident conditions associated with handling, storage, and use of the source housing, it is unlikely that any person would receive an external radiation dose or dose commitment in excess of the dose to the appropriate organ as specified in the following chart:

REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE E L,1 NR-8080-D-801-B DATEi, February 10, 1997 PACE 7 OF B

.t DEVICE TYPE Gamma Gauge j

I MAFETY AMAT.YSIS SITMMARY (con't);

PART OF BODY DQEE 3

Whole body; head and trunk; I

active blood-forming organs; gonads; or lens of eye 15 Rem (0.15 Sv) 4 1

Hands and forearms; feet and ankles; localized areas of skin averaged over areas no larger than 1 square centimeter 200 Rem (2.0 SV)

Other organs 50 Rem (0.50 SV) l Barod on review of the Model SAM 1, and the information and test data cited below, we continue to conclude that the device is acceptable for licensing purposes.

i i

Furthermore, we continue to conclude that the device would be expected to maintain its containment integrity for normal i

conditions of use as specified in this certificate.

REFERENCES:

The following supporting documents for the Model SAM 1 are hereby incorporated by reference and are made a part of this registry i

document.

  • Process Technology, Incorporated's letters dated April 9, 1992, June 15, 1992, August 6, 1992, September 14, 1992, September 29, 1992, and May 17, 1995 with enclosures thereto.
  • Process Technology, Incorporated's facsimile dated and received August 20, 1992.

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REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF DEVICE H Q 2.

NR-8080-D-801-B DATE: February 10, 1997 PAGE B OF B DEVICE TYPE:

Gamma Gauge Uf, ' f! MG ACENCYr U.S. Nuclear Regulatory Commission 7

Date:

Fahruary 10. 1997 Reviewer:

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dpvenL.'aggett l/

Date:

February 10.

1997 Conc 11rrenCO:

ohn W. Lubinski l

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PAGEi NRC FORM 567 U. S. NUCLEAR REOULATORY COMMISSION o*=>

REQUEST FOR A SEALED SOURCE OR DEVICE EVALUATION 1

INSTRUCTIONS: Send tNo request AND a copy of all related letters /opphcohone and drawings to: The Sealed Source Safety Secten. ATTN: Chief, OWFN Mail Stop 6 H3. Change the Ucense Trocking Systern milestone to 19 and seeign to revwwer code I-5.

NOTE: Retain a copy of tNo request with the applicehon and background files.

REQUEST R REGION / LOCATION:

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Pk5.5 TC(

l'77

]I R11 R lli IV RV R HQ LFDCB f

YELEPHONE NUMoER 4

DATE TYPE OF ACTION REQUESTED (Check as..., L)

I APPLOANTS NAME SOURCE REVIEW AMENDMENT OF REGISTRATION SHEET

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MAL CONTROL NUMBERm DEVICE REVIEW NUMBER (S)

LETTER /APPUCATION DATE UCENSE NUMBER (S)

CUSTOM REVIEW

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O COMMEms FOR SSSS USE ONLY REtEWER

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MODEL NUMoERS NUMoER ASelGNED b/t'&

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DAM RECEfvED

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DAE ASSIGNED

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DATE TO FEES Lfl7 y I h

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TYPE OF ACTION (Indicase the number of each type) ft COMMERCIAL DISTRIBUTION (FORMAL) l USE BY A SINGLE APPUCANT (CUSTOM)

SOURCE (9C)

DEVICE (9A)

SOURCE (9D)

DEVICE (98)

NEW NEW NEW NEW

] AMENDMENT

[ AMENDMENT AMENDMENT AMENDMENT

$ NO SAFETY EVALUATION REQUIRED j UCENSING ACTION REQUIRED IF KNOWN NO 8

NO FEES REQUIRED j OTHER (SpecWy)

TOTAL NUMBER OF NOTES fN N 5 N" p7 p,,a '

(OsO)

REVIEW HOURS

'a NUMBER OF DEFICIENCY LETTERS NUMBER OF DEFICIENCY CALLS FOR BILLING PURPOSES ONLY j NEW REGISTRATION-3 PRODUCT INACTIVE -

NAME CHANGE ADDRESS CHANGE ADD TO BILLING REMOVE FROM BILLING FOR FEE USE ONLY TYPE OF FEE FEE CATEGORY

] 9A R 9B 9C U 90 AMOUNT RECEIVED CHECK NUMBER MATANN UPDATED

_ AS REQUIRED j MATSYS UPDATED DATE OF CHECK LOG AS REQUIRED APPROVEDoY DATE REmJRN DATE COMMENTS NRC FORM $6r @93) 2

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