jendco corporation, renewal application dtd 05/10/2007

JENDCO Corporation, Renewal Application dtd 05/10/2007.c o r p o r a t i o n
May 10,2007
Licensing Assistant Section Nuclear Materials Safety Branch US. Nuclear Regulatory Commission, Region I 475 Allendale Road King of Prussia, PA 19406-1415
RE: Request for Renewal of License Number 37-30382-01 i i
To Whom It May Concern:
Attached you will find an application for renewal of JENDCO Corporation Nuclear Regulatory Commission License ## 37-30382-01 .
If after your review you have any questions or need additional information please do not hesitate to contact me.
Best regards,
.JlNIH:O Corporation
,
368 Butler Street Pittsburgh, PA 15223-2123 Phone: (412) 782-1957 Fax: (412) 447-0033 E-mail: [email protected]
US. NUCLEAR REGULATORY COMMISSION
'PUCA7lON FOR DlsTRlBUTlON Of p[EypT PROWCIS RLE APWCATIONS WITn:
APPLICATION FOR MATERIAL LICENSE
YOU ARE L O U T E D I N
MNECTICUT. OEIAWARE. DISTRICT OF COLUMBIA, MAINE. MIRYUND, USACHUSE-TTJ. NEW HAMPSHIRE NEW JERSEY, NEW YORK. PnNsnvmu. IODE ISLAND. OR YERMONT. SEND AFVl+ATlONS TO:
Internet bmdl to bjslOm.gov, and to tho Desk Ofncer, Oflice of Information an( Regulatory Allaim. NEO6-10202. @lSO-OOW), Omce d Management and Budgel WP.hingbDn.DC20503.Na-~toim~snirdormPtioncdlectiondossno
ARQONA, ARKANSAS, CALIFORNIA, COLORADO. HAWAII. IDAHO. UANSAS, LWISIAHA. MONTAN& NEBRNWA, NEVAM. NEW MEXICO. NORTH DAKOTA OKLAJiOW OREQON, PACIFIC TRUST TERRITORIES. SOUTH DAKOTA, mo5. UTAH, WASHINQTON. OR WYOYINQ. SMO *ppucATIoNs TO:
dhplsy a currently valid OMB add number, the NRC may not conduct or sponsor and a person mnot required to rsspondto. the infwmstion cdiection.
T H I s L s A N ~ T l o N F o f ? F h r k . P W b r d m j
O A NEWUCENSE
a AMENMNTTOUCENSENUMBW
- - m . RENEWALOFLICENSENUMBER
~ W H E R E L I E N S E D M A l E R l A L W l U B E U € D o R ~
2 NAMEANDMAlUNGAWREaOFWPUCANr (JndudezIPcDde)
John R . Platschner, Jr. JEHDCO Corporation 368 B u t l e r S t r e e t P i t t sburgh , PA 15223
4 NAME OF PERSON TO BE COMA- ABOVT THIS APPUCATlON
t PROVED BY
IUINOU. IN- WA, MmW MINNESOTA. YUSOURI. OHIO, OR WISCONSIN. SEND mwanows TO:
MATERwuQNslNGBRANol U.S. NUCLEAR RffiULATORY COMMISSON, REGION 111 801 WARRENVILLE RD. usy IL (905324.51
DATE
LlQNslNG ASSLSTANTS- NUaEN? MATERIALS SAFElY BRANCH U.S. NUCLEAR REGULATORY COMMlSSlON. RffiION I 475 ALLPIDALE ROAD mui OF mussIA. PA iwoui415
NUCLUR MATERIALS U C P I W G SECTION U.S. NUCLEAR REGULATORY COMMISSION. REGION IV 611 RYAN PLAZA DRIVE, S U E 400 ARUNGTON.TX 7011-8084
"Only a t temporary job s i t e s o f l i c e n s e e s . "
John R . Platschner, Jr .
h-r I , = m . L 3 s E D s
C€RTlFlCATK)N (Mcntba m p h M by . p p h B THE APPLICANT UNDERSTANDS THAT ALL STATEMENTS AND REPRESP(TATIONS M A E IN THIS AWLlCATlON ARE BINDING
THE APPUCAHFAND ANY O m a A L MHxmNG THE CERTIFICATIW ON BMMF OF THE APPUCANT. NAMED IN ITEM 2. CERTIN'THATTHIS APPMTI(X( IS PREPARED IN CONMRMlWWrm TITLE 10, COM OF rrbERM REGULATIONS. PARTS 30.32,s. 34,s. 38,je. AND 40, AM) THAT ALL INFORMATION CONTANEO HERON IS TRUE AND CORRECTTO THE BEST OF THEIR KNOWLEM;E AND BEUEF.
WARMNO: 18 U.S.C. sEcTw)F( lool ACT OF JUNE 25.1648 (12 STAT 749 MAKES IT A CRIMINAL OFFENSE TO MAKE A W l l L N U Y FMSE STATEMENT OR REPRESPTTATION TO Am DEpARTMplTOR AGENCY OFTHE UMTED S A T E S ASTO ANY MATER WITHIN ITS JURISMCTION.
zm
A. throughN.
A. throughN.
c. Maximum amount which will be possessed at any one time:
A. through N.
. .
6. Byproduct, source, and/or special 7. Chemical and/or physical form nuclear material
A. Iron 55
B. Cobalt 60
C. Nickel 63
D. Krypton 85
A. Sealed sources registered either with the U.S. Nuclear Regulatory Commission under 10 CFR 32.21 0 or with an Agreement State.
B. Sealed sources registered either with the US. Nuclear Regulatory Commission under 10 CFR 32.21 0 or with an Agreement State.
C. Sealed sources registered either with the U.S. Nuclear Regulatory Commission under 10 CFR 32.210 or with an Agreement State.
D. Sealed sources registered either with the U.S. Nuclear Regulatory Commission under 10 CFR 32.210 or with an Agreement State.
8. Maximum amount that licensee may possess at any one time under this license
A. No single source to exceed the maximum activity specified in the certificate of registration issued by the U.S. Nuclear Regulatory Commission or an Agreement State
B. No single source to exceed the maximum activity specified in the certificate of registration issued by the US. Nuclear Regulatory Commission or an Agreement State
C. No single source to exceed the maximum activity specified in the certificate of registration issued by the US. Nuclear Regulatory Commission or an Agreement State
D. No single source to exceed the maximum activity specified in the certificate of registration issued by the US. Nuclear Regulatory Commission or an Agreement State
E. Stontium 90
F. Cadmium 109
G. Cesium 137
H. Cerium 144
I. Promethium 147
E. Sealed sources registered either with the US. Nuclear Regulatory Commission under 10 CFR 32.21 0 or with an Agreement State.
F. Sealed sources registered either with the US. Nuclear Regulatory Commission under 10 CFR 32.210 or with an Agreement State.
G. Sealed sources registered either with the US. Nuclear Regulatory Commission under 10 CFR 32.21 0 or with an Agreement State.
H. Sealed sources registered either with the U.S. Nuclear Regulatory Commission under 10 CFR 32.21 0 or with an Agreement State.
I. Sealed sources registered either with the U.S. Nuclear Regulatory Commission under 10 CFR 32.210 or with an Agreement State.
E. No single source to exceed the maximum activity specified in the certificate of registration issued by the US. Nuclear Regulatory Commission or an Agreement State
F. No single source to exceed the maximum activity specified in the certificate of registration issued by the US. Nuclear Regulatory Commission or an Agreement State
G. No single source to exceed the maximum activity specified in the certificate of registration issued by the U S . Nuclear Regulatory Commission or an Agreement State
H. No single source to exceed the maximum activity specified in the certificate of registration issued by the U.S. Nuclear Regulatory Commission or an Agreement State
I. No single source to exceed the maximum activity specified in the certificate of registration issued by the U.S. Nuclear Regulatory Commission or an Agreement State
J. Americium 241
K. Curium 244
L. Cobalt 60
M. Cesium 137
N. Americium 241
J. Sealed sources registered either with the US. Nuclear Regulatory Commission under 10 CFR 32.21 0 or with an Agreement State.
K. Sealed sources registered either with the U.S. Nuclear Regulatory Commission under 10 CFR 32.21 0 or with an Agreement State.
L. Leak test samples
M. Leak test samples
N. Leak test samples
J. No single source to exceed the maximum activity specified in the certificate of registration issued by the U.S. Nuclear Regulatory Commission or an Agreement State
K. No single source to exceed the maximum activity specified in the certificate of registration issued by the U.S. Nuclear Regulatory Commission or an Agreement State
L. See condition 12
M. See condition 12
N. See condition 12
LB 300 IRL LB 300 IRL
LB 300 L LB 300 L
LB 300 LP LB 300 LP LB 300 LP
LB 300 ML or MLT LB 300 ML or MLT
LB 330 LB 330 LB 330
LB 375 LB 375 LB 375
LB 379
LB 6600 Series
LB 7440 D or F LB 7440 D or F LB 7440 D or F LB 7440 D or F
LB 7444 D or F
LB 7445 D or F . LB 7445 D o r F
LB 7445 D or F LB 7445 D or F
ATTACHMENT A
Cobalt 60 Cesium 137
Curium 244 Cesium 137 Americium 24 1 :Be
Americium 24 1
Cobalt 60
LB 7400 Series (Conveyor Belt) Cesium 137
LB-AS Americium 241
LB-B W LB-B W LB-B W LB-B W LB-B W LB-B W LB-B W
Krypton 85 Strontium 90 Curium 244 Americium 241 Americium 241 Americium 24 1 Americium 24 1
Maximum Activity
P-2608-100/101 SK 1208NZ-287
P-2608-100/101 SK 1208NZ-237
P 2651-201/202 2653.100-000 2663.000-000
2657.000-000 P-2623- 100 P-2611-100
KAC.D3 SIF.Pl CLCL AMC.D2 AMC.D3 AMC. 16 AMC. 17
8 50
500 500
100 500
100 3000 3000 3000
Specific Specific
Both Both
Both Both
3
ITEM 6 - PURF'OSE(S) FOR WHICH LICENSED MATERIAL WILL BE USED
9. AUTHORIZED USE:
A. through K. For possession incident to service for other persons as defined in 10 CFR 20.1003 for:
(1) Installation, initial radiation surveys, relocation, removal from service, dismantling, alignment, replacement, disposal of the sealed source and non-routine maintenance or repair of components related to the radiological safety of ABB Process Automation, Inc.; Apgee Corporation; Berthold Systems, Inc.; Berthold Technologies U.S.A., LLC; Data Measurement Corporation; Flow Measurement Systems; Gamma Instruments; GE Reuter-Stokes, Inc.; Kay-Ray, Inc.; Level Link, Inc.; LFE Corporation; Ohmart Corporation; Ronan Engineering Co.; Rosemount; TN Technologies, Inc.; Sangamo Weston Schlumberger; or Sentrol Systems, Inc. devices that have been registered either with the U.S. Nuclear Regulatory Commission under 10 CRF 32.210. or with an Agreement State.
(2) Leak test sample collection.
L through N. Analysis of leak test samples as a service for other persons as defined in 10 CFR 20.1003.
10. CONDITIONS:
Licensed material listed in Items 6A through 6N May be used at temporary job sites of the licensee anywhere in the United States where the U.S. Nuclear Regulatory Commission maintains jurisdiction for regulating the use of licensed material.
Licensed material listed in Items 6.L. and 6.N. May also be used at the licensee's facility located at 368 Butler Street, Pittsburgh, Pennsylvania 15223.
11. A. Licensed material shall be used by, or under the supervision and in the physical presence of, John R. Matschner, Jr. or individuals who have satisfactorily completed the training program described.
B. The Radiation Safety Officer for this license is John R. Matschner, Jr.
12. In addition to the possession limits in Item 8, the licensee shall further restrict the possession of licensed material to quantities below the minimum limit specified in 10. CFR 30.35(d), 40.36(b), and 70.25(d) for establishing financial assurance for decommissioning.
13. Sealed sources containing licensed material shall not be opened by the licensee.
14. The licensee is authorized to transport licensed material in accordance with the provisions of 10 CFR Part 71, “Packaging and Transportation of Radioactive Material.”
ITEM 7 - INDIVIDUALS RESPONSIBLE FOR RADIATION SAFETY -THEIR TRAINING AND EXPERIENCE
1. Licensed material shall be used by, or under the supervision and in the physical presence of John R. Matschner, Jr. or individuals who have satisfactorily completed the training program (attachment B, C, D, E, F, & G). The licensee shall maintain a written record of all individuals designated as users.
2. All “responsible individuals” working under this license must have written approval from the Radiation Safety Officer and follow a thur f.
a. Complete the attached 40-hour training course. Initial training will consist of a 40-hour training course and each “responsible individual” will be required to pass an examination.
b. After each “responsible individual” has completed the initial 40-hour training course, an annual 16-hour training course is required, (attachment H & I )
c. Formal classroom training as well as hands-on training will be provided by the RSO or another NRC authorized user that has been approved by the NRC.
d. A listing of the specific devices each “responsible individual” has been authorized to work on by the RSO, will be kept on file at JENDCO Corporation.
e. Training for each device that the ‘responsible individual’ has been previously work on will be as follows: First by observation and then supervised by the RSO or an NRC authorized user. Upon completion, written approval from the RSO is required.
f. Fore each new device for which an authorized user does not have experience with, such as newly manufactured devices, the authorized users will be provided training from the manufacturer for each device and the person assigned to this system will be sent for formal training. This individual would then be authorized to train the “responsible individuals” on this device.
ATTACHMENT B
Advanced Automation Biomedical Instrumentation Robotics
-Dean Technical Institute Pittsburgh, PA Associates Degree in Specialized Technology Certified Electrician
-North Catholic High School Pittsburgh, PA
-JENDCO Corporation Engineering Consultants Position - President
January 1997 - Present
North & South America Representative for EG&G BERTHOLD, the worlds largest supplier of nuclear Mold Level Control Systems.
-Included in this representation is the following: Engineering & Design, Technical Support, Sales & Service, Equipment Training and Radiation Training.
-Berthold Systems, Inc. June 1990 - January 1997 Process Control Instrumentation / Nuclear Gauges Positions: - Marketing Director: Complete Berthold Product Line - Steel Marketing Manager: Mold Level Systems - Applications Engineer: System Installation Design - Shipping / Receiving / Service Department: Includes installation, removal, relocation, repair, maintenance, source removal and installation, packaging, leak testing, and radiation survey .
PERSONAL INFORMATION WAS REMOVED BY NRC. NO COPY OF THIS INFORMATION WAS RETAINED BY THE NRC.
Experience:
-0liverio Electric, January 1987 -May 1988 Provided Residential and Commercial Electrical Services.
-Guiding; LirrJlt, Assistant Manager, 1985 - 1987 Designed, and Manufactured Commercial li&ting fixtures.
-M.T.G. Roofins 1982 - 1985 Laborer on Roofmg Projects.
'.
Training Performed By:
W. Boettcher J. Muthmann
K. Sc R uhmann
APPLIED HEALTH PHYSICS - PittsburoJ1. PA
40 - HOUR RADIATION SAFETY OFFICER TRAINING COURSE
Basic Ph sics and Scientific Principles
Radiation Terminology Equations and Calculations Biological Effects of Radiation A.L .A.R.A. Radiation Protection Emermency Procedures Regukions Specific and General License Leak Test Procedures Receiving / Shipping Instructions
Types o ? Radiation
BERTHOLD SYSTEMS, INC. - Pittsbur&, PA
Radiation Safe , Physics and Calculations
Source Removal and Installation Maintenance and Repair Packa ing and Surveying
Installation, Re 'y ocation and Removal of Berthold Gauges
Leak f esting
r i I
A T T A C H M E N T E
Q
u
Q ) *
U
A f ipippu, 9% 15001 -4863 Presents this
BERTHOLD SYSTEMS, I N C . of wfio has sntkfactori& compLeted the prarcri6ed course of instruction includitrfi
RADIATION SAFETY
ATTACHMENT H
Hands-on Training
ATTACHMENT I
-Molecular & Atomic Structures -Isotopes & Radioisotopes -Types of Radiation -Types of Ionizing Radiation -Effects of Particle & Electromagnetic Radiation with Matter -Terms Related to Radiation -Units of Exposure -Equations & Calculations -Biological Effects of Ionizing Radiation - A U R A Principles -Emergency Procedures
Hands-on Training - 8-HOURS
-Installation -Removal -Relocation -Repair -Maintenance -Source Removal & Installation -Packaging -Leak Testing -Radiation Survey
ITEM 8 - TRAINING FOR INDIVIDUALS WORKING IN OR FREOUENTING RESTRICED AREAS
Since there will be no radioactive material at the facility in Pittsburgh, PA, a formal training program will not be needed. All work to-be performed on industrial nuclear gauges will be at the users site. Therefore, training will only be in the capacity of recommendations to the workers as to limit their exposure as defined by ALARA (acronym for “As Low As is Reasonably Achievable”)
1. During installation, removal, relocation and packaging, workers will be supervised to make sure that there will be no unnecessary exposure. This would include making sure the shutter was closed during transport (to be confirmed by survey meter). At this time, recommendations will be made to limit exposure.
2. During repair, maintenance, source removal and installation, workers will be instructed to stay a minimum of 20 feet away from the radioactive source. This will ensure that no worker will receive any unnecessary exposure.
3. During leak testing and surveys, recommendations will be made to limit exposure.
i
ITEM 9 - FACILITIES AND EOUIPMENT
No radioactive materials will be at the facility in Pittsburgh, PA. When any “responsible individual” arrives at a customer facility that has radioactive material, the “responsible individual” will assess the area and make recommendations as “to protect health and minimize danger to life and property.”
Received leak-test samples will be placed in a designated area in our laboratory counting room. Once the analysis is complete with the samples, they will be placed into a storage room that is only accessible to authorized personnel.
ITEM 10 - RADIATION SAFETY PROGRAM
10.1 Personnel Monitoring Equipment
Personnel monitoring equipment is supplied by Landauer, Inc. Glenwood, IL (attachment 5-2 pages)
-each “responsible individual” to receive a TLD body badge to be exchanged at quarterly intervals (attachment K-4 pages) -each “responsible individual” to receive a TLD ring badge to be exchanged at quarterly intervals (attachment L)
10.2 Radiation Detection Instruments and Instrument Calibration
a. Radiation Detection Instrument
-Type ..................... Portable thin-window GM survey meter with external probe -Number Available.. .. ..4 on hand -Radiation Detected ... .Alpha, beta, gamma with external probe; gamma and x-ray with internal detector -Sensitivity Range ...... 0-2000 mR/h -Use ..................... ..Survey and monitoring -Description (attachment M)
b. Instrument Calibration
Landauer - Thinking Outside the Badge bage 1 of 1
ATTACHMENT J PAGE 1
ABOUT US Our Hbtory
Oar W r y
Today, Landauer monitors many of the nation's radiation workers as well as a variety of fore It has a national sales force and employs over three hundred people devoted to services th: protecting personnel from ionizing radiation hazards. But, back in 1954, there was no antici~ company becoming an international service or being ranked among the best small companit and Business Week!
Robert S. Landauer, Jr. started the business in 1954 in his home in Park Forest, Illinois. His radiation monitoring arose as result of accompanying his father on occasion as he made the between medical x-ray therapy installations in the 1930s, consulting with the radiologists, ar their equipment. ARer returning from service in World War II, Landauer worked part-time wit while finishing education at the University of Chicago. After two and a half years of employrr commercial radiation instrumentation field, Bob Landauer took the plunge and started the cc a few borrowed dollars and a prayer."
At first, he did most of the work himself-marking film, processing badges, and preparing rep1 from customers such as Purdue University, General Electric, and Michael Reese Hospital h~ establish the viability of the service, and gradually the company expanded. By 1964, the cor reached a milestone by processing over a million dosimeters.
I In 1968, R. S. Landauer, Jr. and Company merged forces with Techlops, Inc. Through this synergy came the 8mm film system; a smaller, more convenient and user oriented badge design; and an automated film reading system. Landauer's Thenno Luminescent Dosimetry (TLD) service was inaugurated in 1973 as an option to film and a means to improve finger badges. Also in 1973, the first major step towards international expansion came about with the Nagase-Landauer joint venture to provide dosimetry service to Japan. In 1982, Landauer offered its customers the ability to directly access computer data by the use of telephone and modem. In 1988, the company came around full cycle and became independent again as Techlops divested its businesses. In 1992, overseas expansion
optically stimulated luminescence.
&
ATTACHMENT J PAGE 2
>> ABOUT US >> CO
HOME Investors LDRsoluttons Products 8 ~ e h l c e s I
ABOUT US Technical Competence
Gavernaoee
Landauer uses sophisticated technology to accurately analyze each individuaf's exposure. /: utilize computer-cantrolled lasers, image analysis and other sophisticated methods (automa analysis shown in photo to left). Such technology is only a component of the werall picture. visible are the many technical and human interfaces intertwined throughout processing and which provide exposure results that are timely and accurate.
After analysis, test results are entered into the company's computer system, using the unique ID code of each detector as a reference. The computer checks incoming ID codes to make sure they match the information previously entered into the computer's data files. At this point, most of the data is automatically reviewed by the computer, minimizing the likelihood of operator errors. information from each detector is matched and evaluated again at final inspection, at which time the customer's report is generated. All this to assure records are accurate and reliable.
The company employs a number of PhDs and Certified Health Physicists. This staff, together with experienced technicians, ensures that the technology is applied in a competent manner. Systems are continually reviewed and analyz problems are engineered out. A culture that encourages creativrty and empowers individual creates an environment that produces innovation. Neither technology nor people alone can quality laboratory service. It is the company's effective combination of people and equip me^ produces superior results.
Landauer has been a leader in the development of new dos~metry technologies From track detection to laser read TLD devices, laser etched labels, and now OSL technology, Landau1 ready to apply the latest advances.
\ I
, b
ATTACHMENT K PAGE 1
Luxel+ dosimetry service provides x, gamma, and beta radiation monitoring with optically stimulated luminescence (OSL) technology. OSL technology is the newest advancement in passive radiation protection dosimetry that improves on the best features of traditional film and TLD technologies. Neutron detection, processed with Track EtchQ technology, is optional where the CR-39 is incorporated within the Luxel+ dosimeter's clear plastic pack. Luxel+ can be packaged for personnel monitoring, area monitoring, emergency response or other specialized services.
Luxel+ offers complete reanalysis to confirm the radiation dose measurement, imaging of unique filter patterns that provide diagnostic capabilities to identify static or dynamic states during radiation exposure, increased sensitivity and precision, a wide dynamic range of measurement, and excellent long-term stability. In addition to these technological advancements, Luxel+ can be customized to meet the administrative needs of a radiation monitoring program through graphic, color, and packaging design options.
Landauer's service includes a full range of diagnostic evaluation and reporting services, including direct computer access via the Internet to Landauer's database for exposure reports, shipment tracking and account maintenance transactions.
Luxel+ and OSL Technology I 1 Landauer grows the specially formulated aluminum oxide (AI,O,:C) crystalline detector material. The AI,O, detector is then configured into a thin strip sandwiched within a multi- element filter pack. The filter pack is heat sealed within a laminated, light-tight paper wrapper creating an integrated, self-contained packet that is RF (radio-frequency) sealed inside a tamper-proof plastic blister pack to eliminate possible mishandling, light leakage, or lost detection elements.
Luxel+ may be used for up to one year. It is unaffected by heat, moisture, and pressure when the clear blister pack is uncompromised.
Radiation exposure is measured in Landauer's laboratory by stimulating the AI,O, material with selected frequencies of laser light causing it to luminesce in proportion to the amount of radiation exposure. The luminescence measured is applied to a dose algorithm that relies on the response ratios between different filter positions within the dosimeter to discriminate between beta and photon (x and gamma) radiation fields to determine exposure results.
Dose equivalents arising from exposures to photons (x or gamma rays) will have a deep, lens of eye and shallow value reported. Depending on the energy of the x or gamma rays, these values may or may not be equal. Beta exposures are reported only as a shallow dose equivalent.
Analysis The AI,O, detector can be restimulated numerous times to confirm the accuracy of a radiation dose measurement. A full reanalysis is automatically performed for every measurement yielding a dose in excess of 500 mrem (5 mSv).
(Continued)
Luxel@+ Dosimeter for X, Gamma, Beta, and Neutron Radiation
m s (mu) The filter pack imaging area renders unique filter patterns that provide qualitative information about conditions during exposure. Imaging to identify static, dynamic, or contamina- tion conditions is automatically performed for all beta and low-energy photon measurements yielding a dose in excess of 500 mrem (5 mSv). Imaging capabilities are inconclusive at energies exceeding 150 keV.
Reanalysis or imaging at doses less than 500 mrem (5 mSv) can be requested. lmaging is not available for doses less than 50 mrem (500 pSv).
A static exposure image indicates the dosimeter may not have been worn at the time of exposure. This is verified by the distinct grid patterns in the filter pack imaging area. A static exposure implies that an accidental exposure may have occurred with the dosimeter.
Technical Speafkations
A dynamic exposure image indicates the dosimeter was moving at the time of exposure. This is verified by the blurred grid patterns in the filter pack imaging area. A dynamic exposure implies that the dosimeter was worn at the time of exposure, and the reported dose is valid.
Static Emmure
Jyna ...., Exposure
. R.dbtbna p)labn I
besumd @ m d - Ray) B . b P r t M . Nmubvn
Dsrscbr '4403 Optional NelbaP 144 detector it-side dosimeter (Aluninun Oxide) (Ahrnirun Oxide) (cR-39)
&tically Simulated Luninescence Optically Stimulated Luninescencc Chemical etcHng followed by mhod ( E L ) (=L) back cwlbing (Track-etdp)
EnwOlw 150 keV to in exxss of 10 MeV Fast: 40 keV to 40 MeV D.cc# 5 keV to inexesof40 MeV (Eqmed asAmge Enem ThennaV htemediate: 025 eV to 40 keV
Do5a 1 mrem to 1000 rem 10 mrem to 1 000 rem Fast 20 mrem to 25 rem (200 pSv to 250 mSv)
Ywunmnt (10pSv to 10Sv) (100 psv to 10 Sv) Thermal' Mennediate: 10 mlgn to 5 rem
Raw (1 00 pSv to 50 mSvj
Deep Dose (HplO) *15% at the 95% confidence interval for photons above 20 keV I
Accuracy Shallow Dose (Hp 0.07) *15% at the 95% confidence intenral for photons above 2( d and beta parHcles Above 200 keV
NVLAP (NVLAP Lab Code 100518-0) for Whole Body (ANSI HPS N13.11-2001) in the comprehensive subcategory A#ndlblbne 'GeneraP in all categories including VI when neLltron component is added; and for extremity (ANSI HPS N13.32-1995).
HSE (Health and Safety Execulve) United Kingdom approved for Whole Body (OSL) a d Whole Body Neutrola. DOELAP (Department of Energy Laboratory Accreditation Program).
Luxek and Track Etch Technology The optional Neutrak detector available for an additional charge is a CR-39 (ally1 diglycol carbonate) based, solid- state nuclear track detector that measures exposure due to neutrons. It is not sensitive to x, beta or gamma radiation, and is sealed inside the Luxel+ plastic blister pack to eliminate possible mishandling or lost detection elements. The CR-39 is laser engraved for permanent identification to assure chain-of-custody.
The fast neutron option uses a polyethylene radiator for fast neutrons that records recoil protons resulting from neutron interactions in the dosimeter. The thermal1 intermediate neutron option has a dosimeter design intended for fast,
intermediate, and thermal neutrons. The left arba of the chip uses a polyethylene radiator for fast neutrons while the right area uses a boron loaded Teflona radiator fast, intermediate, and thermal neutrons that records alpha particles resulting from neutron interactions in the dosimeter.
During analysis in our laboratory, the CR-39 is etched for 15 hours in a chemical bath to enlarge exposure tracks. The fast neutron dose is measured by counting the tracks generated as a result of the proton recoil with the polyethylene radiator, while the thermal1 intermediate dose is measured by counting the alpha tracks generated with the boron radiator.
ATTACHMENT K PAGE 3
Luxelm+ Dosimeter for X, Gamma, Beta, and Neutron Radiation
Administrative Design Features The look of Luxel+ can be specialized through the selection of various combinations of graphic formats and background options to help identify groups and wear dates. Optional features such as department (series) color-coding and company logos that can further specialize dosimeters are available for an additional charge.
The name of the account and worker, and a dosimeter placement icon indicating correct placement of the dosimeter is shown on the front of the Luxel+ basic design. The account and participant numbers, wear date, dosimeter use location, serial number, and the dosimeter and component bar codes, all ensuring chain of custody, appear on the back of the dosimeter.
Background and Graphic Format Options Choose between any combination of four background options and three graphic formats. Background options are no background (default), Dogs, Sky or Trees. Graphic formats are Side Bar (default), Comer or Cross. The graphic formats change in color with each exchange frequency and each season has its own unique icon to help distinguish wear dates. Use the default color sequence, or select among six colors for a custom color sequence.
Department Groupings (Series) Department groupings within accounts are available for an additional charge. This service segregates departments on dosimetry reports, prints the department name on the face of the dosimeter, and a series code on the back of the dosimeter. The department's name on the face of the dosimeter is printed over a gray line graphic (default) or can be color-coded for easy identification in a choice of six different colors.
Dosimeter Placement lcons lcons on the face of the dosimeter identify the correct placement of the dosimeter, and a written description is included on the back of the dosimeter for verification. lcons include all whole body and extremity use, area monitoring, and a special icon designed for fetal monitoring.
Collar and waist dosimeters have color-coded icons for quick and easy placement when two dosimeters are required to be worn at the same time. One example is EDE 1, a special dose calculation where one dosimeter is worn at the waist level under a lead apron and one dosimeter is worn at the collar level outside the lead apron. Special dose calculations permit departure from Landauer's standard dose assessment protocol in order to provide a more accurate estimation of radiation dose under special circumstances as determined by the Radiation Safety Officer. Special dose calculations can be applied to an individual, a department (series), or to an entire account.
Graphic Color Coding By Exchange Frequency
Sample loons Show Dosimeter Placement
ATTACHMEIWT K PAGE 4
Luxel@+ Dosimeter for X, Gamma, Beta, and Neutron Radiation - - Holder A Finite Element Analysis (FEA) study was used to develop the most durable holder available. The dosimeter simply snaps into the holder.
The standard holder has an alligator clip for secure fastening 1 to clothing. In areas where no metal material is allowed, a clip made from all plastic can replace the standard plastic and metal alligator clip. Area monitor holders have Velcroe
tabs with adhesive backing for easy surface placement.
Padcaging Luxel+ can be packaged for personnel monitoring, area monitoring, emergency response or other specialized services. Standard packaging ships each dosimeter individually wrapped in cellophane along with a card containing account and worker information that can be customized with a message to the entire account, a department (series), or a specific worker. Unused dosimeters returned to Landauer still wrapped in cellophane are automatically reported as unused (excluding control dosimeters). 1 Optionally, dosimeters can be sealed within a heavy-duty vinyl tamper resistant pouch that can have multiple slots to permit several methods of attachment for use with a snap-on strap and alligator clip or various length straps for extremity use. Emergency response packaging includes a customer
1 designed informational card sealed within the vinyl pouch.
ATTACHMENT L
Landauer's ring dosimetry service provides comprehensive extremity radiation monitoring for -- workers required to manually manipulate or to work in close proximity to radioactive materials and radiation producing equipment. Landauer was the first facility to receive accreditation by the National Institute of Standards and Technology through NVLAP (NVLAP Lab Code 100518-0) for ring and wrist dosimeters when the extremity dosimetry standards were first established.
Landauer's ring measures exposure due to x, beta, and gamma radiation with TL (thermoluminescent) technology. The TLD is the highest efficiency dosimeter of 100% TL grade lithium fluoride, with no binder.
Landauer dosimetry service includes a proven full range of diagnostic evaluation and reporting services, including direct computer access via the Internet to Landauer's database for exposure reports, shipment tracking and account maintenance transactions.
Achmced Design The TLD is safely encapsulated inside the identification cover. No separation of the TLD from the cover is possible, so the identity of the chip and the wearer is always maintained. The cover and TLD are independent of the ring base.
The identification on the cover is laser engraved preventing the print from smearing, peeling, or washing off. Rings can be worn in dry or wet working conditions and cold sterilized without compromising the integrity of the dosimeter. Information on the cover includes the account, participant, and serial numbers, the worker's name, the wear date and exchange frequency, the size, and on what hand the ring is to be worn.
Rings are available in small, medium and large to comfortably fit any user, and smooth edges allow rings to slide and fit inside surgical gloves. The ring base color changes (red, blue or black) each wear period to help identify wear dates.
Department Groupings (Series) Department groupings within accounts are available for an additional charge. This service segregates departments on dosimetry reports and laser etches the deparhnent (series) code on the ring cover.
TLD Technology Landauer's therrnoluminescent (TLD) ring dosimeter measures radiation exposure due to x, beta, and gamma radiation with a lithium fluoride chip. During analysis in our laboratory, the TLD chip is heated causing it to become luminescent in proportion to the amount of radiation exposure. The luminescence is measured and a report of exposure results is generated. The glow curve of the readout that permits a more conclusive evaluation of radiation exposure can be retrieved and analyzed before the exposure report is generated if any anomaly appears.
--
Accurate Calibration Accurate determination of exposure is supported by calibrations using anatomically correct hand phantoms. This permits determination of the radiation scatter pattern caused by the many small bones of the hand and thus helps to ascertain dose to the hand based on the amount found on the ring dosimeter. Custom calibrations can be made to measure the low energies encountered with laboratory instruments such as electron microscopes and x-ray diffraction units.
AnalyslsAssurance Rings are scanned before processing using optical character recognition to accurately identify and track each dosimeter from receipt to report. The TLD is read automatically by laser, and the process is overseen by skilled technicians. The glow curve of the readout that permits a more conclusive evaluation of radiation exposure can be retrieved and analyzed before the exposure report is generated if any anomaly appeare f
Technical Specifications Highest efficiency dosimeter of 100% TL grade lithiun fluoride, with no binder - one TLD per ring. Energy Range: Photon (x or gamma ray) - greater than 15 keV. Beta particle expressed as average energy - greater
than 200 keV. Dose Measurement Range: Photon (x or gamma ray) - 30 mrem to 1,000 rem
(300 pSv to 10 Sv). Beta particle - 40 mrem to 1,000 rem
\ /
Lurvey Meters & T r o b E ATTACHIYENT H
*ur eyor 2000TM Portable Survey Meter L he Surveyor 2000 111odel is a portable survey I I I C L C ~
designed for gamma and x-ray with internal probe- . I
plus measurements of alpha, beta and gamma count rate with the appropriate external GM probe. I The Surveyor 2000 combines an internal energy compensated GM tube (for the 2 R/h range) with
1 choice of external GM probes to meet or exceed th survey instrument requirements of lOCFR 35 fo Nuclear Medicine use.
The unit checks HV to insure the detector is operating at its proper voltage. An anti-saturation circuit keeps the meter reading off scale when th, detector saturates in a high radiation field. Automatic dead time compensation assures the accuracy of higher exposure rate reading for linear response on all ranges.
The Surveyor 2000 is the perfect Survey Meter for your Nuclear Medicine Department and eliminate. the need for two survey instruments for high and low radiation readings.
* Alpha, beta, gamma and x-ray detection
* Internal GM tube and optional external probe * Anti-saturation circuit * Built-in audio * Counts up to 2000 mR/h * Exceeds 10CFR35 requirements
Radiation Detected: Alpha, beta, gamma, and x-ray depending upon detector used.
Detector: Choice of G M probes, external; GM tube, internal
Range: Five linear ranges of:
0-0.2 mR/h 0-240 cpm
0.2 mR/h 0-2,400 cpm
0-20 mR/h 0-24,000 cpm
0-200 mR/h 0-240,000 cpm
0-2000 mR/h (internal detector)
Accuracy: Within 10% of reading for Cs-137 when calibrated according to NRC Reg. Guide 10.8
Energy Response: *20% from 40 keV to 1.2 MeV (internal detector)
High Voltage: Electronically stabilized, factory set ac 900 V. Contains self-test to verify detector H V power supply-
I Visit us o n cllr wrb a t
1 l k M 8 U k b L K l l ' l 1 U N
5250-00 19 Surveyor 2000 Rate Meter
Warm-up Time: None
Saturation: Typically r 1000RIh on all ranges for most GM probes;( >5 R/h for pancake G M probes)
Response Time: Switch-selectable, optimized for each range, 0-90% of final reading as follows:
Range Fast Slow
XO.l 6 s e c 2 5 s e c
X1 2 sec 6 sec
X10 1 sec 3 sec
Xl00 < I sec 1 sec
X1000 c1 sec 1 sec
Size: 4.25" x 8" x 6.8" (10.8 x 20.3 x 17.3 cm) including handle and probe clip.
Weight: 2.2 pounds (1 kg) excluding external probe
ATTACHMENT B PAGE 1
Certificate No. 043 1 4 1
J END C 0 C 0 R P 0 RAT1 0 N Attention: John Matschner 362 Butler St. Pittsburgh, PA 15223-21 23
- CERTIFICATE OF CALIBRATION 63 12 West Oakton Street Morton Grove. IL 60053-2723 Telephone: 847-965- 1999
Fax: 847-965-1 99 1 w mi. us
Manufacturer: BICRON - Model: SURVEYOR 2000 - Serial No.: C067C
Pro be( s) : SWGM
CALIBRATION DATA
If the accuracy of a scale is not within +/-IO% but is within +l-20% a correction factor is supplied.
Check Source: Not Applicable
Temperature: 21 "C Relative Humidity: 43 % Barometric Pressure: 1005 mbar
Comments: The xO.1, XI scales were electronically referenced to the x10 scale at 1 mR/hr = 1653 cpm.
Calibrated by: Date: 10/6/06
Calibration Frequency: Annual Recalibrate by: 10/6/07
*SOURCE 1. CS-137 2. CS-137 3. Am-241 4. Cf-252 5. Electronic 6. Other Manufacturer U.S. Nuclear Eon Corp. Amersham Amersham Model CCs-D-20E 64-764 AMC 13446 100 Serial Number 722 7510 LA FTC-CF-001 Activity 11.5 Ci 100 mCi 100 mCi 1801 pg Date 111 994 5/2/78 6/3/84 10/8/85
Calibration authorized by Illinois Department of Nuclear Safety License No. IL-01429-01 and meets the requirements of ANSI 323-1978 and MIL-STD- 45662A. Exposure rate traceable to N E T with MDH model 1015 SN 109 transfer instrument. Radcal Cert. of Conf. 20300.
ATTACHMENT N PAGE 2 -
63 I2 West Oakton Street Morton Grove, IL 60053-2723 Telephone: 847-965- I999
Fax: 847-965-1 991
- CERTIFICATE OF CALIBRATION
M. KSI. US
Certificate NO. 043 1 42
J EN DC 0 C 0 R P 0 RAT1 0 N Attention: John Matschner - Model: SURVEYOR 2000 362 Butler St. * Serial No.: C475A Pittsburgh, PA 15223-2123 Probe@): BICRON SWGM, Sn: B858X
Manufacturer: B IC RO N
CALIBRATION DATA
If the accuracy of a scale is not within +/-IO% but is within +/-20% a correction factor is supplied.
Check Source
Not Applicable
22 "C Relative Humidity: 51 % Barometric Pressure: 988 mbar
The xO.1, XI scales were electronically referenced to the x10 scale at 1 mR/hr = 1600 cpm.
*SOURCE 1. CS-137 2. CS-137 3. Am-241 4. Cf-252 5. Electronic 6. Other Manufacturer U.S. Nuclear Eon Corp. Amersham Amersham Model CCs-D-20E 64-764 AMC 13446 100 Serial Number 722 7510 LA FTC-CF-00 1 Activity 11.5 Ci 100 rnCi 100 rnCi i a o i pg Date 111994 5/2/78 6/3/84 I 018185
Calibration authorized by Illinois Department of Nuclear Safety License No. IL-01429-01 and meets the requirements of ANSI 323-1 978 and MIL-STD- 45662A. Exposure rate traceable to NlST with MDH model 1015 SN 109 transfer instrument. Radcal Cert. of Conf. 20300.
ATTACHMENT N PAGE 3 - - CERTIFICATE OF CALIBRATION
RSSI 6 3 12 Wesr Oakton Street Morron Grove, lL 60053-2723
847-965-1999
JENDCO CORPORATION Attention: John Matschner 362 Butler St. Pittsburgh, PA 15223-2123
Manufacturer: B I C RON - Model: SURVEYOR 2000
~ Serial No.: B566Y Probe(s): BICRON SWGM, Sn: BO922
CALIBRATION DATA
If the accuracy of a scale is not within +/-I 0% but is within +/-20% a correction factor is supplied.
Temperature: 22 "c Relative Humidity: 23 % Barometric Pressure: 1000 mbar
Comments: The xO.1, XI scales were electronically referenced to the x10 scale at 1 mR/hr = 1607 cpm.
Calibrated by: Date: 12/5/06
*SOURCE 1. CS-I37 2. CS-I37 3. Am-241 4. Cf-252 5. Electronic 6. Other Manufacturer U.S. Nuclear Eon Corp. Amersham Amersham Model CCs-D-20E 64-764 AMC 13446 100 Serial Number 722 7510 LA FTC-CF-001
Date 111 994 5/2/78 6/3/84 10/8/85 Activity 11.5 Ci 100 mCi 100 mCi i a o i l.lg
Calibration authorized by Illinois Department of Nuclear Safety License No. IL-01429-01 and meets the requirements of ANSI 323-1978 and MIL-STD- 45662A. Exposure rate traceable to NlST with MDH model 1015 SN 109 transfer instrument. Radcal Cert. of Conf. 20300.
ATTACHMENT N PAGE 4 - - CERTIFICATE OF CALIBRATION
RSSl 6 3 I2 West Oakton Street
Morton Grove, lL 60053-2723 847-965-5-1999
Fax 347-965-1991
JENDCO CORPORATION Attention: John Matschner 362 Butler St. Pittsburgh, PA 15223-2123
Manufacturer: BICRON
: Model: SURVEYOR 2000
CALIBRATION DATA
If the accuracy of a scale is not within +/-IO% but is within +/-20% a correction factor is supplied.
Temperature: 22.5 "c Relative Humidity: 31 % Barometric Pressure: 988 mbar
Comments: The xO.1, XI scales were electronically referenced to the XI 0 scale at 1 mR/hr = 1637 cpm.
c / = Calibrated by: d-dw
Model CCs-D-20E 64-764 Manufacturer U S . Nuclear Eon Corp.
Serial Number 722 Activity 11.5 Ci 100 mCi Date 111 994 5/2/78
Date: 12/14/06
Recalibrate by: 12/14/07
3. Am-241 4. Cf-252 5. Electronic 6. Other Amers ham Amersham AMC 13446 100 7510 LA FTC-C F-00 1 100 rnCi 1801 pg 6/3/84 10/8/85
Calibration authorized by Illinois Department of Nuclear Safety License No. IL-01429-01 and meets the requirements of ANSI 323-1 978 and MIL-STD- 45662A. Exposure rate traceable to NlST with MDH model 1015 SN 109 transfer instrument. Radcal Cert. of Conf. 20300.
Radiation Survey Meter I Radiation Safety 1 RSSI Page 1 of2
ATTACHMENT 3 PAGE 1
RSSI calibrates over 3000 models of radiation survey meters at our in-house calibration facility. Our fixed range offers consistent, high quality calibration meeting ANSI 323-1 978 and MIL-STD-45662A. RSSl’s calibration team ensures that calibration of your instrument is completed within 5 business days and the instrument is packed securely for insured shipment back to you. In situations where you need your radiation survey meter returned to you quickly, one day turnaround and overnight shipping is available.
0 Authorized by IEMA License IL-01429-01
Approved by Canadian Nuclear Safety Commission R-I17 Cs-137 exposure rates between 0.08 mR/hr and 40+ R/hr Cf-252 neutron dose rates between 0.1 mrem/hr and 30 mrem/hr Ranges can be extended electronically to meet manufacturers’ specifications Surface emanation rate efficiencies determined for alpha and beta emitters Free reminder letters when your radiation survey meter is due for calibration
In addition to radiation survey meter calibration, RSSl’s technicians can repair each meter we calibrate. We maintain an extensive library of manuals and schematics and a large inventory of radiation survey meter parts. Our manuals library and parts inventory allows us to repair your radiation survey meter and return it to you within our standard turn around time.
We calibrate all makes of radiation survey meters, including:
Ludlum
Victoreen
Bicron
Eberline
I Radiation Survey Meter 1 Radiation Safety 1 RSSI - ATTACHWENT 0 PAGE 2
Cost for calibrating a basic 3-scale instrument is $70 plus shipping and handling.
For more information on RSSl’s calibration services, please contact us.
Page 2 of2
“Rss1 - A NATIONAL LEADER IN RADIAlION SAFETYAND RADIOLOGICAL H
6312 W. OAKTON Sr. M O U T O N GROVE. If 60053 r E L : 847-965-1999 FAX: 847-965-1991
C m m q t - t ,?:COE Radiation Sarely Se-~ icss nc
Home I Consulting I Laboratory I Calibration I Radon I Contact Us
http://www.rssi.us/calibration. htm 5/11/2007
, I
BICRON + NE 6801 Cochran Road Solon, Ohio 44139 USA Tel: (216) 248-7400 Toll Free: 800472-5656 Fax: (216) 349-6581
http://www.bicron.corn
A
.AL& CONSULTAiTS, INC. 9523-27 Avenue Edmonton, Alberta T61.J 1B2 Canada 40319442557 (Fax) 4031944-2555 Xllan Seitz
I
GTS INSTRUMENT SERVICES, INC. 2045 Route 286 Pittsburgh, PA 15239
James Christopher 3 12/733- 1900
HEALTH PHYSICS NORTHWEST 11535 South West 67th Skeet Tigard, OR 97223 5031620-66 17 Fax: 684-5548 Mickey
HEALTH PHYSICS SERVICES, INC. 1350 Piccaro Drive, Suite 304 Rockville, MD 20850 30 1/670-18 18 or 800/969-4774 Richard Brown
W. H. HEN'KEN INDUSTRIES, PIC. 4 15 Lillard Road klington, TX 76012 8 17/26 1-5566 Fax: 261 -5555 Scott Henken
STAN A. HUBER CONSULTANTS, INC. 200 N. Cedar Road N. Lenox, IL 60451 8151485-6161 (Fax) 815/485-4433 Stan Huber
JRT CALIBRATION SERVICES 1200 East High St. - Suite 1 1 1 Pottstotvn, PA 19464
Harold Harbison 6 101327-96 10
K Sr S ASSOCIATES 1926 Elm Tree Drive Nashville, TN 372 10 615/883-9760 or 3001522-2325 (Fax) 9 13/789-8758 Phil Green (Repair) %chard Hardison (Calibration)
MID AMERICA CALIBUTIONS 5500 Buena Vista, $101 Shawnee Mission, KS 66205 9 131789-8757 (Fax) 9 131789-8758 Karl Artinger
NC SYSTEMS, I8C. 5785 kapahoe - Suite D Boulder, CO 80303
CharIes H. Rose
NWT ANALYTIC Sr CO 1724 Holmes Street Livermore, CA 94550-60 12 5 1014437967 Don Wadsworth
3031442-73 58
JSULT, ,TION
W I A T I O N DETECTION COMPANY 162 Wolfe Road Sunnyvale, CA 94086
Richard H. Holden 408/73 5-8700
SAINT-GOBAIN INDUSTRIAL CERAMICS
f I RADIATION MANAGEMENT
SERVICES, RYC. ( R M S ) 757 McKay Road, Unit #I Pickering, Ontario Canada L 1 W 3C8
Michael White 9051428-8060 Fax: 425-845 1
RADIATION SAFETY c9r CONTROL SERVICES 62 Portsmouth Avenue Sfmtham,M-I 03885
Eric Darois
6031778-287 1
SOUTHEASTERN ATOMICS LAB 1 3 54 N. W. 53 rd Avenue Gainesville, FL 32601
Don Price 9041372-97 16
TECHMCAL SERVICES GROUP, N C . 675-C Progress Center Avenue Lawrenceville, GA 30243
Alan Faniba 4041822-9 1 17
R.iM. WESTER & ASSOCIATES, N C . 215 Indacom St. Peters, MO 63376
Tjaden Meyer 3 141928-9628
10.3 Ouerating and Emergency Procedures
a. Every “responsible individual” will be given a set of emergency procedures to follow in case an emergency occurs while the “responsible individual” is at the customer facility. For emergency and operating procedures see (attachment P-2 pages)
b. Leak test kits will be performed with approved kits
Leak test certificate will contain the following information (Example: attachment Q)
-customer name, address and contact person -identification of the instrument by manufacture, type model number and serial number -identify the individual who performed the leak test along with date performed -identify the individual who analyzed the leak test along with date performed -identification of the source by radioisotope, activity, serial number -results indicating greater than or less than 0.005 micro curie of activity
10.4 Commercial Leak Test Kits
The JENDCO leak test kit will include the following items:
1. A single wipe 2. Instructions for safe use of this kit, step-by step procedures for making wipes and
procedures for returning the wipes back to JENDCO Corporation. (Attachment R)
3. A form for the customer to fill out that identifies the customer’s name, license number, source and device (by manufacturer, model number, and activity) wiped, and the name of the individual who made the wipes. (Attachment S)
4. A container used for holding and shipping the leak test kit
10.4 Records
Copies of the leak test certificates will be kept on file. (Attachment T) Analyzed leak test wipes will be kept in our storage room for a period of 1 year.
ATTACHMENT R
JENDCO LEAK TEST INSTRUCTIONS Add '/z inch water to tube, return swab, shake and dissolve reagent, discard excess reagent/water. Complete information on certificate and mark tube with source serial number, isotope, and activity. Perform wipe test wiping the nearest accessible area of the source, return swab and tighten cap.
Package and return to: JENDCO Corporation, 368 Butler St., Pittsburgh, PA 15223.
1. 2. 3. 4. Observe radiation safety procedures. 5.
This is to acknowledge the receipt of your letterlapplication dated
ShLL-&7 , and to inform you that the initial processing which includes an administrative review has been performed
#--- 7;- 2’03 2;; z - c v d There were no administrative omissions. Your application was assigned to a technical reviewer. Please note that the technical review may identify additional omissions or require additional information,
0 Please provide to this office within 30 days of your receipt of this card
A copy of your action has been forwarded to our License Fee & Accounts Receivable Branch, who will contact you separately if there is a fee issue involved.
Your action has been assigned Mail Control Number /y-as-i 5 , When calling to inquire about this action, please refer to this control number. You may call us on (610) 337-5398, or 337-5260.
NRC FORM 532 (Rl)

jendco corporation, renewal application dtd 05/10/2007

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