IR 015000017/1993001
| ML20057B755 | |
| Person / Time | |
|---|---|
| Site: | 07109036, 015000017 |
| Issue date: | 09/17/1993 |
| From: | Cain C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20057B751 | List: |
| References | |
| 15000017-93-01, 15000017-93-1, NUDOCS 9309230225 | |
| Download: ML20057B755 (4) | |
Text
/
.
.
APPENDIX U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
Inspection Report:
150-00017/93-01 Docket:
15-000017 Certificate of Compliance: 71-9036 Licensee:
Source Production & Equipment Co., Inc.
113 Teal Street St. Rose, Louisiana 70087 Facility Name: Source Production and Equipment Co., Inc.
Inspection At: St. Rose, Louisiana Inspection Conducted: August 20, 1993 Inspector: Mark R. Shaffer, Radiation Specialist
..
Approved:
,/xffd)
GafLV ()?l/7/99 hirles L. Ca'in, Chief Date ~
~
luclear Materials Inspection Section
,
Inspection Summary Areas Inspected:
This was a special, unannounced radiation safety inspection of activities relating to the statements, representations, and procedures outlined in an application dated November 13, 1989, which was submitted as supporting information for Certificate of Compliance For Radioactive Materials Packages No. S036.
Summary of Inspection Findings:
Activities performed pursuant to Certificate of Compliance No. 9036
.
appeared to be consistent with the procedures outlined in the applicstion dated November 13, 1989.
Attachment:
Attachment - Persons Contacted and Exit Meeting
i
>
.
d
'
.
-2-DETAILS 1 PROGRAM OVERVIEW Source Production & Equipment Co., Inc., (SPEC) holds a State of Louisiana Radioactive Material License for its activities involving sealed sources for use in industrial radiography.
SPEC has also applied for, and received from NRC, Certificates of Compliance (C0C) for Radioactive Materials Packages.
This inspection was a review of selected activities regarding C0C No. 9036 issued for the Model C-1 package.
2 PACKAGE DESIGN CONTROL AND DEMONSTRATION OF COMPLIANCC The Model C-1 packaging consists of an overpack and a uranium shielded radiographic source changer. The source changer configuration is that of a rectangular box 9 inches high x 7.5 inches wide x 7 inches deep.
During this inspection, v.he inspector verified these physical dimensions by direct measurements of the source changer. The specified maximum gross weight of the source changer b $5 pounds.
Yhe outer foam filled overpack is a 12 gallon open heal 20 or 22 gauge steel drum. The specified maximum gross weight of the overpack is 100 pounds (so m e changer within the overpack).
During this inspection, a random sampling of packages which were prepared for shipment were weighed to verify compliance with C0C No. 9036.
SPEC's scale (Detecto Scales Inc., Model 854, Serial 790-2688) was used to verify the weight of the radiographic source changer e th and without the overpack. The i
inspector observed that the weight of the source changer alone was 50 pounds, while the weight of the source changer and the overpack was observed to be 69 pounds (the weight of just the overpack was 19 pounds).
As noted above, C0C No. 9036 specifies that the maximum gross weight of the radiographic source changer is 45 pounds.
Therefore, the inspector observed a difference of 5 pounds from the specified maximum gross weight. This discrepancy was discussed with SPEC personnel.
SPEC personnel informed the inspector that they were in fact aware that the weight of the source changer was 50 pounds rather than the 45 pounds specified in the applicable C0C and supporting documentation, but they felt that this minor difference in weight was irrelevant because SPEC never ships the source changer without its overpack. And, as noted above, the inspector verified that the weight of the source changer and the overpack was well below the specified maximum gross weight of 100 pounds.
Through discussions with SPEC personnel, the inspector noted that SPEC also ships radiographic sources overseas to customers in several foreign countries.
SPEC personnel stated that all shipments made domestically or exported to foreign markets are made in an authorized container / packaging accompanied with its associated C0C and Certificate of Competent Authority.
SPEC personnel also stated that on some occasions a " consolidated overpack" container is also used to export packages when shipments are limited to one package per shipment.
In these cases up to four NRC approved containers are packaged
.
s
.
.
.
.
-3-within a consolidated overpack so as to meet the "one package per shipment" limitation.
The inspector reviewed some of SPEC's procedures for performing tests demonstrating the ability of the Model C-1 Type B packaging to withstand accident conditions during transportation.
In particular, the inspector reviewed SPEC's procedures for testing the package's ability to withstand a free drop through a distance of nine meters (30 feet) onto a flat, essentially unyielding, horizontal surface, striking the surface in a position for which maximum damage is expected.
'
The inspector observed the drop tower constructed at SPEC's facility which~is
used to perform these tests. The tower is used to raise a package, by use of a cable and pulley system, to a height of at least 30 feet before being t
dropped on to a concrete pad. The height of'the drop is measured by SPEC personnel prior to the drop to ensure that the 30 feet minimum drop requirement is achieved. The above mentioned tower currently erected at the SPEC facility is not the same tower used to perform the original drop tests on the C-1 package.
However, SPEC personnel informed the inspector that the
-
height of 30-feet was also verifitd prior to dropping each package from the previous tower.
3 SPECIAL FORM SOURCE MODIFICATION AND REPAIR PROCEDURES
,
Also reviewed during this inspection was SPEC's procedures for maintenance and repair of sources that are shipped in packaging approved by NRC for transportation.
Specifically, the inspector reviewed SPEC's procedures for repairing and/or replacing the source pigtail connector on industrial radiography sources. This is a procedure which involves the crimping and splicing of the connector cable and is one which is NRC approved.
SPEC personnel stated that this practice is performed infrequently (approximately twice in 2 years), and is only performed on selected sealed source connectors which are in otherwise excellent physical condition prior to performing the-repair.
Based on interviews with SPEC personnel, the inspector noted that-these procedures appeared adequate, r
.
.
,
A
/
'
~
...
.
ATTACHMENT l PERSONS CONTACTED 1.1 Source Production and Equipment Company (SPEC)
- Joe Busch, Facility Manager
- R.D. Donny Dicharry, President 1.2 NRC Personnel
- Mark R. Shaffer, Radiation Specialist
- Denotes individuals present during site exit briefing on August 20, 1993.
,
2 EXIT MEETING A site exit briefing was conducted on August 20, 1993, with those individuals identified in Section 1 of this attachment.
The inspector reviewed the specific findings as presented in the report.
,
!
i
!
!
I
.
.