IR 015000039/1981010
| ML15224A524 | |
| Person / Time | |
|---|---|
| Site: | Oconee, 02700047, 015000039 |
| Issue date: | 11/02/1981 |
| From: | Macarthur T, Potter J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | DUKE POWER CO. |
| Shared Package | |
| ML15224A520 | List: |
| References | |
| 15000039-81-10B, NUDOCS 8203080434 | |
| Download: ML15224A524 (4) | |
Text
Cp REGL,
MoUNITED STATES
aNUCLEAR REGULATORY COMMISSION REGION 1l 101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 Special Report:
WASTE PACKAGING INSPECTIONS OF LICENSEE-SHIPPERS REPORT NO.81-10B Disposal Site:
Chem-Nuclear Systems, In P. 0. Box 726, B rnwell, South Carolina 29812 Do&
t T. rt ur Da e SIgned Approved by:
uJ'
J. P. P er, Chief, Materials Radiation D te Signed Pr ction Section Division of Engineering and Technical Inspection SUMMARY Inspection Dates: September 28, 1981 visit to Chem-Nuclear Waste disposal site, Barnwell, South Carolina for unannounced inspections of licensee-shipper Areas Reviewed: Each licensee-shipper vehicle was inspected for compliance with U.S. Department of Transportation (DOT)
and Nuclear Regulatory Commission (NRC) regulations as follows:
(1) shipping paper requirements; (2) DOT Plac arding requirements; (3) radiation levels; (4) removable contamination; (5) DOT marking and labeling requirements for packages; (6) DOT and NRC requirements for external package features, (7) prohibited articles or contents, and (8) compli ance with other applicable regulatory requirement Results: Of the eight areas inspected involving this shipment, one violation was identifie PDR ADOCK 05000269 G
DETAILS Persons Contacted R. Sappington, South Carolina, DHEC W. House, South Carolina, DHEC J. Ott, CNSI Exit Interview The Projects inspector was informed by telephone of the results of this inspection by the resident inspector during the week of September 28, 198 The resident inspector indicated he would be in communication with the licensee on this matte.
General The NRC inspection consisted of a review of the shipping papers, radiation surveys of the vehicle, contamination surveys and radiation surveys of selected package 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 vehicles were inspected for appropriate marking, labeling, tightness of seals, integrity of package construction and any evidence of leakag Chem-Nuclear assigns a control number for each shipment upon arrival at the site. These numbers are called "arrival survey numbers" (AS No.)
and are used by the inspectors to identify licensee-shippers during this inspectio.
Shipments Inspected One shipment inspected on September 28, 1981, was observed to have greater than one-half percent (0.5%) free standing liquid in three container.
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 follows:
Material shipping name
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49 CFR 172.100/172.200/172.202 Material class
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49 CFR 172.200/172.202 Name sequence
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49 CFR 172.200/172.202 Total quantity (volume)
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49 CFR 172.200/172.202 Limited quantity
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49 CFR 172.200/172.203
Name of each radionuclide
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49 CFR 172.203 Physical and chemical form
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49 CFR 172.203 Activity in curies
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49 CFR 172.203 Category or label
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49 CFR 172.203 Notation of NRC/ERDA package approval
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49 CFR 172.203 Proper certification
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49 CFR 172.204 In addition to the above, 49 CFR 177.817 requires carriers to maintain the above shipping papers readily available for inspection and recognizable by authorities in case of an acciden No violations or deviations were disclose.
Each 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
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49 CFR 177.842 Loaded so as to avoid spillage
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49 CFR 177.842 Properly blocked and braced
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49 CFR 173.392/177.842 LSA vehicle survey
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49 CFR 177.843 No violations or deviations were disclose. Maximum Radiation Levels The truck was surveyed for maximum radiation levels in the normally occupied portions of the vehicle, in a vertical plane at the edge of the flatbed 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. Each shipping cask was surveyed at the surfac No levels were in noncompliance with 49 CFR 173.393 limit.
Packaging The shipment was examined for conformance with DOT marking and labeling requirements. External features of the packages were examined for confor mance with DOT and NRC requirements as noted below:
Low specific activity (LSA) packaging
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49 CFR 173.392 Tight packages - Ltd. Qt CFR 173.391 or 173.392 No release of material
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49 CFR 173.392/173.393 Radioactive material markings
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49 CFR 172.310 Security seals
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49 CFR 173.393 Gross weight requirements
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49 CFR 172.310 Proper shipping name
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49 CFR 172.100/172.300 LSA labeling
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49 CFR 173.392 Cask design specifications
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49 CFR 173.393a
No violations or deviations were disclose.
Other Transportation Requirements The shipment was 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 transfere One violation was disclosed.