ML20052F983
| ML20052F983 | |
| Person / Time | |
|---|---|
| Site: | 02700047, Millstone |
| Issue date: | 10/28/1981 |
| From: | Mcarthur T, Potter J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20052F961 | List: |
| References | |
| 27-0047-81-10A, 27-47-81-10A, NUDOCS 8205140209 | |
| Download: ML20052F983 (4) | |
Text
UNITED STATES 8
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NUCLEAR REGULATORY COMMISSION o
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REGION 11 101 MARIETTA ST., N.W SulTE 3100 ATLANTA, GEORGIA 30303 o
Special Report: WASTE PACKAGING INSPECTIONS OF LICENSEE-SHIPPERS REPORT NO. 81/10A l.icensee-Northeast Nuclear Energy Company Shipper:
Disposal Site: Chem-Nuclear Systems, Inc.
P. O. Box 726, Barnwell, South Carolina 29812 Barnwell, SC 29812 Inspector: )d Oc k N
7 T. C. MacAr h r, adiation Specialist Date Signed Approved by:
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J.
Potter, Chief, Material Radiation Protection Date S(gned ection, Technical Inspection Branch Engineering and Technical Inspection Division
SUMMARY
Inspection Date: September 29 1981, visit to Chem-Nuclear Waste disposal site, Barnwell, South Carolina for unannounced inspections of licensee-shippers.
Areas Reviewed: Each licensee-shipper vehicle was inspected for compliance with Department of Transportation (DOT) and Nuclear Regulatory Commission (NRC) regulations as follows:
(1) shipping paper requirements; (2) DOT placarding requirements; (3) radiation levels; (4) removable contamination; (5) 00T marking and labeling requirements for packages; (6)'00T and NRC requirements for external l
package features, (7) prohibited articles or contents, and (8) compliance with other applicable regulatory requirements.
Results: Of the eight areas inspected involving this shipment, one violation was identified.
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8205140209 820122 PDR ADOCK 05000245 0
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9 DETAILS 1.
Persons Contacted R. Sappington, South Carolina, DHEC W. House, South Carolina, DHEC J. Ott, CNSI 2.
General The.NRC inspection consisted of a review of the shipping papers, radiation-survey of the vehicle, contamination surveys and radiation level surveys of selected packages.
General surveys and observations were conducted to determine if the-vehicle had proper placards, proper seals, and if any -
obvious safety hazards existed. The contents of the vehicle were inspected for appropriate marking, labeling, tightness of seals, integrity of package construction and evidene.e of leatage.
Chem-Nuclear assigns a control number for each shipment upon arrival at the site. These numbers are called " arrival survey n' umbers" (AS No.) and were used by the inspecter to identify licensee-shippers during this inspection.
3.
Shipments Inspected One shipment was inspected on September 29, 1981, and was observed to have greater than one-half percent (0.5%) free standing liquid in three con-tainers.
4.
Shipping Papers The shipping papers were reviewed.for completeness and to ascertain-if the contents of the shipment were properly identified, and if emergency notifi-cation procedures and instructions were included as required under 49 CFR 172, Subpart C.
Specific requirements for shipping papers were reviewed as i
follows:
Material shipping name 49 CFR 172.100/172.200/172.202 Material class 49 CFR 172.200/172.202 Name sequence 49 CFR 172.200/172.202 Total quantity (volume) 49 CFR 172.200/172.202 i
Limited quantity 49 CFR 172.200/172.203 49 CFR 172.203 Name of each radionuclide 49 CFR 172.203 Physical and chemical form Activity in curies 49 CFR 172.203 i
Category or label 49 CFR 172.203 Notation of NRC/ERDA package approval 49 CFR 172.203 l
Proper certification 49 CFR 172.204 1
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In addition to the above,'49 CFR 177.817 requires carriers to maintain the above shipping papers readily available for recognition and inspection.
by authorities in case of an accident.
No violations or deviations were disclosed.
5.
.The vehicle was inspected for.conformance with DOT placarding requirements (49 CFR 172, Subpart F and 49 CFR 173.392).
The vehicle was also inspected for compliance with the following:
Maximum transportation index of 50 -
49 CFR 177.842 Loaded so as.to avoid spillage 49 CFR 177.842 Properly blocked and braced 49 CFR 173.392/177.842-LSA vehicle survey 49 CFR 177.843 No violations or deviations were disclosed.
6.
Maximum Radiation Levels The vehicle was surveyed for maximum radiation levels in the normally occupied portions of the vehicle, in a plane at the edge of the flat bed or at the surface of the closed vehicles; in a vertical plane six feet from the sides of the vehicle where possible, and on the surface of a representative package.
Shipping casks were surveyed at the surface.
No levels were in violation of 49 CFR 173.393 limits.
7.
Packaging A representative sampling of packages was examined for conformance with DOT marking and labeling requirements.
External features of the packages were examined for conformance with DOT and NRC requirements as noted below:
Low specific activity (LSA) packaging 49 CFR 173.392 Tight packages - Ltd. Qty.
49 CFR 173.391 or 173.392 No release of material 49 CFR 173.392/173.393 Radioactive material markings 49 CFR 172.310 Security seals 49 CFR 173.393 Gross weight requirements 49 CFR 172.310 Proper shipping name 49 CFR 172.100/172.300 LSA labeling 49'CFR 173.392 Cask design specifications 49 CFR 173.393a No violations or deviations were disclosed.
3 8.
Other Regulatory Requirements Certain packages were examined for compliance with 10 CFR 30.41(c) requirements concerning the transferee's license authority to receive the type, form and quantity of the byproduct material transferred.
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