ML21133A225

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Hopewell Designs, Inc. - NRC Form 592M, Inspection Report 15000010/2021001 (DNMS)
ML21133A225
Person / Time
Site: 15000010
Issue date: 05/12/2021
From: Ryan Craffey
Division of Nuclear Materials Safety III
To: Vanderpool C
Hopewell Designs
References
IR 2021001
Download: ML21133A225 (1)


See also: IR 015000010/2021001

Text

NRC FORM 592M

(10-2020)

U.S. NUCLEAR REGULATORY COMMISSION

Materials Inspection Record

Page 1 of 1

NRC Form 592M (10-2020)

1. Licensee Name:

Hopewell Designs, Inc.

2. Docket Number(s):

150-00010

3. License Number(s)

GA-1434-1

4. Report Number(s):

2021-001

5. Date(s) of Inspection:

May 12, 2021

6. Inspector(s):

Ryan Craffey

7. Program Code(s):

03226

8. Priority:

2

9. Inspection Guidance Used:

IP 87126

10. Licensee Contact Name(s):

Chris Vanderpool, RSO

11. Licensee E-mail Address:

chris.vanderpool@hopewelldesigns.com

12. Licensee Telephone Number(s):

770-667-5770

13. Inspection Type:

Initial

Routine

Announced

Non-Routine

Unannounced

Temporary Job Site

Field Office

Main Office

14. Locations Inspected:

Remote

15. Next Inspection Date (MM/DD/YYYY):

TBD

Normal

Reduced

Extended

No change

16. Scope and Observations:

This was an announced inspection of an irradiator manufacturer authorized by the State of Georgia to use and

possess sealed sources in registered and custom devices incident to installation, removal, calibration, relocation,

repair, testing, and servicing of such devices as well as training and R&D on such devices at its facility in Alpharetta,

and at temporary job sites within Georgia jurisdiction. The licensee conducted these activities at temporary job sites

in NRC jurisdiction under the terms of a reciprocity request filed in December 2020 for calendar year 2021. The

scope of this inspection was limited to an evaluation of licensed activities (upgrading a dosimeter irradiator including

a new source shield, which necessitated the handling and transfer of Am-241:Be and Cl-36 sealed sources) at

Wright Patterson Air Force Base outside of Dayton, Ohio.

The inspector first observed the licensee's field engineer perform dry runs of the handling operation using dummy

sources. The engineer had several long-handled tools at his disposal, as well as blocks of water-extended polyester

for neutron shielding, an electronic dosimeter for real-time exposure monitoring, a rem ball neutron detector and a

pancake probe GM meter (all operational and calibrated within the last year). The engineer wore a gamma, beta,

and neutron-sensitive whole-body dosimeter as well as two gamma-sensitive extremity dosimeters and latex gloves

in the event of contamination from sealed source leakage. The inspector interviewed the engineer, and found him to

be knowledgeable of radiation protection principles, operation of radiation monitoring equipment, and the design and

operation of the irradiator. The inspector performed independent surveys on contact with the old source shield and

noted gamma exposure readings of up to 180 uR/hr, and minimal neutron exposure readings.

The inspector then observed the engineer perform the source transfer, using the same tools, techniques, and

monitoring equipment as before. The engineer used appropriate ALARA practices throughout, including adequate

postings and restricted area control and continuous monitoring of exposure rates during the operation. The engineer

remotely collected and analyzed leak tests of both sources, using the GM meter and a jig that ensured a standard

geometry for the counts. The engineer found no evidence of residual contamination in excess of regulatory limits.

He then transferred both sources into the new shield and confirmed its adequacy with gamma and neutron surveys.

The inspector performed similar surveys, noting neutron readings of up to 1.5 mrem/hr prior to final shield assembly

(with minimal neutron readings afterwards), and gamma readings of up to 150 uR/hr. The inspector also performed

independent surveys in unrestricted areas during the source handling operations. No gamma or neutron exposures

in unrestricted areas exceeding limits to members of the public were noted.

No violations of NRC requirements were identified as a result of this inspection.