strata, inc.; (amend 13) nrc form 313 numbers 5-11 … · laboratories model xfb-3) 6. purpose for...

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5. Radioactive Material DNMS Byproduct, source, and/or Chemical and/or physical form Maximum amount that licensee special nuclear material may possess at any one time under this license A. Cesium-137 A. Sealed sources (Troxler A. 8 millicuries per source and drawing No. A-102112, CPN 270 millicuries total. Model CPN-131) B. Americium-241 B. Sealed neutron sources B. 100 millicuries per source and (Troxler drawing No. A-102451, 1250 millicuries total. A 102113, A-100608, A-100337, CPN Model CPN-131, AEA Technology QSA, Inc., Model No. AMNV997; Isotope Product Laboratories Model No. Aml. No.2) C. Cesium-137 C. Sealed sources (Troxler C. 9 millicuries per source and 9 drawing No. A-102112 millicuries total. D. Cadmium-109 D. Sealed sources (Amersham D. 40 millicuries per source and Corp., Model CUCP. 1, CUC. D1, 80 millicuries total. CUC. P1; Isotope Product Laboratories Model XFB-3) 6. Purpose for which licensed material will be used: A. and B. B. c. D. To be used in Troxler Electronic Laboratories, Inc. Model No. 3400 Series, 4300 Series, 3401, 3411 Band #450 gauges to measure moisture/density of construction materials and Campbell Pacific Nuclear Corporation Model MC Series or 500 Series gauges for moisture/density determinations. To be used on Troxler Electronics Laboratories, Inc. Model 3241 and 4300 Series gauge for asphalt content measurements To be used in Troxler Electronic Laboratories, Inc. Model4640 Series Thin Layer Density gauge for measurement of density of asphalt overlays. To be used in NITON XL MODEL 309 and XLP Series x-ray fluorescence analyzers to check lead in paint or soil analysis and Columbia Scientific Industries Corporation (CSIC) Models HEPS, LEPS, DO S, SSPS, and SLPS Probes (Fomtefl 2: S86tforx- ..... mmedlate Releale ray fluorescence analysis. Nonnal Release NON-PUBLIC 0 Related 0 A. 7 Se··,,.t;ive Internal 0 Other. cot% \ y Rewiev .-.r; Date: A \' , -------.:.18'110 0 ............ l"YC pe4111)1.:1181Af111111C'Y D OI'8W"NON a1lni8H tew.ION D aseaJ&b apJpeWWI 0 onand

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5. Radioactive Material DNMS

Byproduct, source, and/or Chemical and/or physical form Maximum amount that licensee special nuclear material may possess at any one time

under this license

A. Cesium-137 A. Sealed sources (Troxler A. 8 millicuries per source and drawing No. A-102112, CPN 270 millicuries total. Model CPN-131)

B. Americium-241 B. Sealed neutron sources B. 100 millicuries per source and (Troxler drawing No. A-102451, 1250 millicuries total. A 102113, A-100608, A-100337, CPN Model CPN-131, AEA Technology QSA, Inc., Model No. AMNV997; Isotope Product Laboratories Model No. Aml. No.2)

C. Cesium-137 C. Sealed sources (Troxler C. 9 millicuries per source and 9 drawing No. A-102112 millicuries total.

D. Cadmium-109 D. Sealed sources (Amersham D. 40 millicuries per source and Corp., Model CUCP. 1, CUC. D1, 80 millicuries total. CUC. P1; Isotope Product Laboratories Model XFB-3)

6. Purpose for which licensed material will be used:

A. and B.

B.

c.

D.

To be used in Troxler Electronic Laboratories, Inc. Model No. 3400 Series, 4300 Series,

3401, 3411 Band #450 gauges to measure moisture/density of construction materials

and Campbell Pacific Nuclear Corporation Model MC Series or 500 Series gauges for

moisture/density determinations.

To be used on Troxler Electronics Laboratories, Inc. Model 3241 and 4300 Series gauge

for asphalt content measurements

To be used in Troxler Electronic Laboratories, Inc. Model4640 Series Thin Layer Density

gauge for measurement of density of asphalt overlays.

To be used in NITON XL MODEL 309 and XLP Series x-ray fluorescence analyzers to check

lead in paint or soil analysis and Columbia Scientific Industries Corporation (CSIC)

Models HEPS, LEPS, DO S, SSPS, and SLPS Probes (Fomtefl 2: S86tforx- ..... mmedlate Releale

ray fluorescence analysis. Nonnal Release

NON-PUBLIC 0 A.~ Ser"~sitive-Securlty Related 0 A. 7 Se··,,.t;ive Internal

0 Other. cot% \ y Rewiev • .-.r; ·--~~c::z Date: A \' ,

-------.:.18'110 0 ............ l"YC

pe4111)1.:1181Af111111C'Y D OI'8W"NON

a1lni8H tew.ION D aseaJ&b apJpeWWI 0

onand

7. Individual( s) Responsible for Radiation Safety Program and Their Training Experie! . ~U~ ~ 7 ~ 2~ JE ~ The Radiation Safety Officer (RSO) for this license is Michael J. Connolly. The RSO has successfiJJtMS

completed one of the training courses described in Criteria in the section entitled "lndividual(s)

Responsible for ~adiation Safety Program and Their Training and Experience- Radiation Safety Officer" in

NUREG-1556, Vol. 1, Rev. 1, dated November 2001.

8. Training For Individuals Working In Or Frequenting Restricted Areas.

Before using licensed material, authorized users will have have successfully completed one of the

training courses describes in Criteria in the section entitled "Training for Individuals Working In or

Frequenting Restricted Areas" in NUREG-1556, Vol. 1, Rev. 1, dated November 2001.

9. Facilities and Equipment

Answer Not Required by Applicant.

10. Radiation Safety Program- Instruments

We will have access to and use a radiation survey meter that meets the Criteria in the Section entitled

"Radiation Safety Program - Instruments" in NUREG-1556, Vol. 1 Rev. 1, dated November 2001, in the

event of an incident.

10. Radiation Safety Program- Material Receipt and Accountability

Physical Inventories will be conducted at intervals not to exceed 6 months, to account for all sealed

sources and devices received and possessed under the license.

10. Radiation Safety Program- Occupational Dosimetry

Either we will maintain, for inspection by NRC, documentation demonstrating that unmonitored

individuals are not likely to receive a radiation dose in excess of 10 percent of the allowable limits in 10

CFR Part 20 or we will provide dosimetry processed and evaluated by an NVLAP-approved processor

that is exchanged at a frequency recommended by the processor.

10. Radiation Safety Program- Operating and Emergency Procedures /

We will implement and maintain the operating and emergency security procedures in Appendix H of

NUREG-1556, Vol. 1 Rev. 1 dated November 2001 and provide copies to all gauge users and at each job

site.

PUBUC 0 Jmmedlate Release ~Nonnal Release

~ IE li: IE 0 W IE 1ii1

JUN 2 7 2014 ~ 10. Radiation Safety Program- Leak Test

DNMS A. Sealed sources shall be tested for leakage and/or contamination at intervals not to exceed the

intervals specified in the certificate of registration issued by the U.S. Nuclear Regulatory Commission

under 10 CFR 32.210 or by an Agreement State.

B. In the absence of a certificate from a transferor indicating that a leak test has been made within the

intervals specified in the certificate of registration issued by the U.S. Nuclear Regulatory Commission

under 10 CFR 32.210 or by an Agreement State prior to the transfer, a sealed source or detector cell

received from another person shall not be put into use until tested and the rest results received.

C. Sealed sources need not be tested ifthey are in storage and are not being used. However, when they

are removed form storage for use or transferred to another person, and have not been tested within the

required leak test interval, they shall be tested before use or transfer. No sealed source shall be stored

for a period of more than 10 years without being tested for leakage and/or contamination.

D. The leak test shall be capable of detecting the presence of 0.005 microcurie (185 Becquerels) of

radioactive material on the test sample. If the test reveals the presence of 0.005 microcurie (185

Becquerels) or more of removable contamination, a report shall be filed with the U.S. Nuclear

Regulatory Commission in accordance with 10 CFR 30.50 © (2), and the source shall be removed

immediately from service and decontaminated, repaired, or disposed of in accordance with Commission

regulations. The report shall be filed within 5 days of the date the leak test result is known with the U.S.

Nuclear Regulatory Commission, Region IV, 612 east Lamar Blvd., Suite 400, specify the source involved,

the test results, and corrective action taken.

E. Tests for leakage and or contamination shall be performed by persons specifically licensed by the U.S.

Nuclear Regulatory Commission or an Agreement State to perform such services. In addition, the

Licensee is authorized to collect leak test samples but not perform the analysis; analysis of leak test

samples must be performed by persons specifically licensed by the Commission or an Agreement State

to perform such services.

F. Records of leak tests results shall be kept in units of microcuries and shall be maintained for 3 years.

G. Sealed sources or source rods containing licensed material shall not be opened or sources removed or

detached from source rods or gauges by the licensee, except as specifically authorized.

10. Radiation Safety Program- Maintenance

We will implement and maintain procedures for routine maintenance of our gauges according to each

manufacturer's recommendation sand instructions.

PUBLIC a ) mmedlate Release llir" Normal Release

NON-PUBUC C A.3 Sensitive-Security Related C A.7 SensiUve Internal 0 Other: •

r ·· ·:-q/L-"""' ~~1~ ~ ~

10. Radiation Safety Program- Transportation

No answer required with this application.

11. Waste Disposal- Gauge Disposal and Transfer

No answer required with this application.

~ ~u~ ~/2o~ ~@ ..._ DNMS

PUBLIC Cfimmediate Release ~ Nonnal Release

NON.PUBLIC IJ A.3 Sensitive-Security Related IJ A.7 Sensitive Internal

IJ Other: lil /,.... --1f1 ~ f'.•vie·N·~r· ... ~-· !)"'<!~.~