ML20151L234

Registry of Radioactive Sealed Sources & Devices,Safety Evaluation of Sealed Source for Models Ag,Bg,Cg & Dg. Certificate:NR-8091-S-813-S

ML20151L234
Person / Time
Issue date:	07/21/1997
From:	NRC
To:
References
SSD, NUDOCS 9708060292
Download: ML20151L234 (3)

Text

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REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SEALED SOURCE i -

! NO.:'NR-8091-S-813-S DATE: July 21, 1997 PAGE 1 OF 2 4

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SEALED SOURCE TYPE: Radiography Source Assemblies j MODEL: 'AG, BG, CG, DG 4 ,

MANUFACTURER / DISTRIBUTOR: Cumberland Research Corp. )

Port Norris, NJ 08349 -

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! ISOTOPE: MAXIMUM ACTIVITY:

Cobalt-60 50 curies (1.85 TBq) j Iridium-192 100 curies (3. 7 TBq) .

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4 LFAK TEST FREOUENCY: 6 Months ,

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] PRINCIPAL USE: (A) Industrial Radiography  ;

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CUSTOM SOURCE: YES X NO 9700060292 970721

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l REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SEALED SOURCE NO.: NR-8091-S-813-S' DATE: ' July 21, 1997 PAGE 2 OF 2 SEALED SOURCE TYPE: Radiography Source Assemblies 1

DESCRIPTION: l Model. For Use In:

AG Automation Industries' Model 10, 20, 30, 40AB, 100 and 103 with Gamma Industries' disconnect BG Automation Industries' Model 50B Series and 110AB with Gamma Industries' disconnect CG Automation Industries' Model 60C Series with I Gamma Industries' disconnect  ;

I DG Automation Industries' Models 40AD Series with Gamma Industries' disconnect The above sources are identical to Cumberland Research Corporation's Model A, B, C and D source assemblies except that ,

they have the Gamma Industries' disconnect instead of the  !

Automation Industries' disconnect.

I SAFETY ANALYSIS

SUMMARY

As of the effective date of this document, the Model AG, BG, CG and DG Radiography Source Assemblies are no longer manufactured and distributed by Cumberland Research Corporation. Cumberland Research Corporation's materials license expired on July 31, 1977-and the company is no longer in business.

These source assemblies were approved for licensing purposes by the Atomic Energy Commission (AEC) on March 15, 1971. There is insufficient information on fi)e for this device to perform a safety evaluation. Therefore, this certificate is being reissued without further review based on the original review and approval issued by AEC.

$h l ,i j g;gf ' , '%;b ' , N _,A ,.'; $:j.: . - *0' PAGE 1 al 1000 PORMOST,:

) U.S. NUCLEAR REGULATORY COMMISSION l S. paal ; p .

W l i REQUEST FOR A SEALED SOURCE OR '

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DEVICE EVALUATION

1: ,' , , .n 44 R eseeeuwususso: Send 011e request AND e copy of el reisted leseroloppeoatione end eastrige to: The Sealed Source Safety Secton, ATTN: CNef, -

{ Qp OWFN GAIS Step 8 NB. Change sie unense Traaldne System entestone to 19 and seeign to reviewer code 14.~

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REGION / LOCATION: t i , ,g . b4 M h/4 M-

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}D TYPE OF ACTION REQUESTED (CInsett as . m ^

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' URCE REVIEW NDMENT OF

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REGISTRATION SHEET j aant cosmeOLNUMmWe00) DEVICE REVIEW ggy I '

i umunsaPeucanON mTE UCENSE NUMoER(S) CUSTOM REVIEW i ovre ,

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FOR 8888 USE OfA.Y/ -

! REVIEWER MODEL NUMoERS p $ pp fwa [p NUMoER AmeGNED l l' hi A'$ i Mi 6f' k . ito $,

onie nEmveD m TEAbo m Eb mTE To runs k

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! /l CORA4ERCIAL DISTRIBUTION (FORMAL) l USE SY A SINGLE APPLICANT (CUSTOM)

SOURCE (9C) DEVICE (9A) SOURCE (90) DEVICE (98)

NEW NEW NEW NEW

/ AAENDMENT AMENDMENT AMENDMENT AMENDMENT s *'

d NO SAFETY EVALUATION REQUIRED j LICENSING ACTION REQUIRED IF IOlOWN -

NO FEES REQUIRED NO'

] OTHER (SpedW l

TOTAL NUMBER OF NOTES 4g4 l REVIEW HOURS C4-*1f ,

l NUMBER OF p ., ut (*< M DEFICIENCY LETTERS  ;

NUMBER OF +:

DEFICIENCY CALLS

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FOR 8E1300 PURPOSES Oft.Y NAME CHANGE ADDRESS CHANGE W REGISNM -

ADD TO BILLING d NW MCM-REMOVE FROM BILUNG FOR FEE USE 004.Y TYPE OF Put FEE CATEGORY r . s x SA C 98 9C - R 90 _

AMOUNT MEmVED CHEM NUMoER MATANN UPDATED F j i o . .

AS REQUIRED

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(/ AS REQUIRED APPROVeDeV V mTE RETURN DATE co sens e

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i Note to File:

Based on the fact that Cumberland Research Corp.'s (CRC) material license expired on July 31,1977 and the company is no longer in business, the following registration certificates have been changed to inactive -

status:

FROM: TO:  ;

NR-245-D-101-U NR-8091-D-801-S  !

NR-245-S-102-U NR-8091-S-802-S NR-245-S-103-U NR-8091-S-803-S NR-245-S-104-U NR-8091-S-804-S

_ l NR-245-S-105-U NR-8091-S-805-S I NR-245-S-106-U NR-8091-S-806-S NR-245-S-107-U NR-8091-S-807-S I NR-245-S-108-U NR-8091-S-808-S i NR-245-D-109-U NR-8091-D-009-S j NR-245-D-110-U NR-8091-D-810-S NR-245-S-111-U NR-8091-S-811-S i i

NR 245-D-112-U IJR-8091-D-812-S  !

NR-245-S-113-U NR-8091-S-813-S NR-245-D-114-U NR-8091-D-814-S  !

I NR-245-S-115-U NR-8091-S-815-S l

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NR-245-D-116-U NR-8091-D-816-S l NR-245-S-117-U N R-8091-S-817-S NR-245-S-118-U NR-8091-S-818-S NR-245-S-119-U NR-8091-S-819-S These devices / sources were approved for licensing purposes by the Atomic Energy Commission (AEC) in the late 60's and early 70's. There is insufficient information on file to perform safety evaluations. The background files only contained the registration certificate and NUDOCS only had licensing information.

Archive files form Oak Ridge contain original AEC registration, mostly just correspondence letters between AEC and CRC, a lot of engineering drawings, but little, if any, technicalinformation. Therefore, these l certificates are being reissued without further review based on the original review and approval issued by j AEC. '

fh Syv Eric Compton, Engineering Aide f)6 Sealed Source Safety Section p[

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