ML20028G011
| ML20028G011 | |
| Person / Time | |
|---|---|
| Issue date: | 01/28/1983 |
| From: | Nelson G, Norderhaug L, Pang F, Png F, Weider A, Zurakowski P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20028G008 | List: |
| References | |
| 110-02838-83-01, 110-2838-83-1, NUDOCS 8302070311 | |
| Download: ML20028G011 (3) | |
Text
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U. S. NUCLEAR REGULATORY C0ftilSSION I-REGION V Report No. 110-02838/83-01 (IE-V-544)
Docket No. 110-02838 License No. XSNM-1955 Licensee: Mitsui & Company (U.S.A.) Inc 200 Park Avenue New York, New York 10166 I
Facility Name:
Container Freight Station 5110 7th Street Oakland, California t
Inspection Conducted: January 13, 1983 f
Date of Last Inspection: Not Applicable Type of Inspection: Routine, Announced
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Inspectors:
W. Vieder, Safeguards Auditor
/DapeSigned
/k/sen
/-28-8K i
[>( Ntilson, Chemist Date Signed T. F. 9 t-%%S F. Pang, Radidtion Specialist Date Signed tcdL.
24 Jc% P 3 P. Zurgkowski, Radiation Specialist Date Signed
/!%T Approved:
[
d r
V mm L'. R. Nordprhaug, Chief N _ - ")
Date Signed Safeguards Branch Inspection Summary:
Inspection on January 13, 1983 (Report No. 110-02838/85-01 (IE-V-544))
Areas Inspected: Verified shipping drum identification and tamper seal numbers to packing lists; confirmed gross drum count; examined shipping container and tamper seal integrity; compared total special nuclear material quality with the amounts authoirzed by NRC export license; monitored external radiation levels; and checked each drum for possible surface contamination.
This inspection involved 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> of onsite time by four NRC inspectors.
l Results: No items of noncompliance were noted.
8302070311 830131 PDR XPORT XSMi-1955 PDR
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DETAILS 1
1.
-Persons Contacted i
H. Henderson, Specialist, Hazaadous Materials Transportation, General Electric' Company, San Jo a. California
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-J. Mahoney, Container Services, James E. Dillon & Associatas, Inc.
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2.
Action on Previous Inspection Findings Not applicable.
3.
Exit Interiview j
i The findings and observations were discussed with Mr..Henderson at the l
conclusion of this inspection. No major defects were observed to.
visible drum surfaces.
Radiation readings were in the: acceptable levels. No surface contamination was dete'ted. However, most seals c
were not drawn snug to the bolt locking lug and all dangled from one inch lengths of wire.
(Paragraph 4.c).
l Mr. Henderson made note of the comments for a. report to his management.
I 4.
Verification of Special Nuclear Material Import / Exports - MC 85300B l
j No items of noncompliance were noted.
i a.
All 253 BU-7 drum identification and corresponding tamper seal 1
numbers were confirmed with General Electric Company's export packing lists JPN-9104F, 9157F, and 9158F. There were no discrepancies between them.
b.
-All visible drum surfaces, except the tops and bottoms, were j
viewed for obvious signs of significant damage or out of specification j
conditions. None were noted.
c.
The type "E" copper and brass tamper seals were examined for method 7
of application and integrity. All seals were intact and none 4
crimped or disfigured. However, most of~the seals dangled from one inch lengths of wire because they were not drawn snug i
against the bolt locking lug. Wire to a snug seal will rupture with one or two turr.s of backing off the bolt locking lug.
Enough free play in tb sealing wire, on the other hand, can be used to open a so-called " sealed" d"um with out wire breakage.
The latter j
works in conjunction with other known conditions, and these were discussed with Mr. Henderson.
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f d.
Gross quantities of special nuclear material were compared to the amount authorized by NRC export license XSNfi-1955.
Such infonnation is given here for congarison.
Expressed (in kilograms)
Uranium Enriched Uranium 235 Authorized:
17,414 3.95 625 This Shipment:
11,726.8 3.18*
405.8
- Averaged over enrichemrn s ranging from 1.22 to 3.92 per cent.
e.
Health and safety checks for detectable surface contamination and excessive radation levels were performed on each shipping drum.
No removable alpha or beta-gamma contamination was detected.
Radiation readirigs were about 0.50 mr/hr to no more than 1.2 mr/hr at the surfaces of containers and about 0.5 mr/hr at three feet from the containers with backgound contributions from surrounding clusters of palleted drums.
The radiation readings were higher than those recorded on the shipping documents and container labels. This was true because the information on the shipping documents was determined for each individual container.
Radiation level readings for palleted containers are influenced by all of the containers on the pallet.
The accepted difference in the palleted versus single-container radiation hvels was discussed with a licensee representative at the time of the inspection.
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