IR 015000039/1980021
| ML19330A777 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry, 02700047, 015000039 |
| Issue date: | 06/20/1980 |
| From: | Peery W, Troup G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | TENNESSEE VALLEY AUTHORITY |
| Shared Package | |
| ML19330A776 | List: |
| References | |
| 15000039-80-21, NUDOCS 8007290401 | |
| Download: ML19330A777 (4) | |
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NUCLEAR REGULATORY COMMISSION n
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101 MARIETTA ST N.W sulTE 3100 o
ATLANTA, G EORGIA 30303
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Special Report: WASTE PACKAGING INSPECTIONS OF LICENSEE-SHIPPERS REPORT NO. 80-21 Reference:
TI2840/1, (Rev. 1), " Waste Packaging Inspections", 10/10/79 Licensee-
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Shipper:
Tennessee Valley Authority Attn:
H. G. Parris Manager of Power 500A Chestnut Street Tower II Chattanooga, TN 37401 Disposal Site:
Chem-Nuclear Systems, Inc.
o27co o 4 7 P. O. Box 726, Barnwell, SC 29812 Docket No. 15000039
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Inspector:
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'o W. W. Peery, Raff) tion Specialist, FF&MS Section, Date' Signed FF&MS Bra c1 Approved by:
- . M,9 b//c[bo G. L. T'ro0p,' Act/ng Chief, REW Section, Date Signed FF&MS Branch SUMMARY Inspection Dates: April 28,1980 visit to Chem-Nuclear Waste disposal site, Barn-well, South Carolina for announced inspection of licensee-shipper and continuation of the inspection on May 1,1980, at the Browns Ferry Nuclear Plant site.
Areas Reviewed: Each licensee-shipper vehicle was inspected for compliance with Department of Transportation (DOT) and Nuclear Regulatory Commission (NRC) regula-tions as follows: (1) shipping paper requirements; (2) DOT Placarding requirements; (3) radiation levels; and (4) DOT marking and labeling requirements for packages.
Results: Of the four areas inspected involving this shipment, one apparent item
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of noncompliance was identified (Severity Level I - radiation levels on surface of closed exclusive use vehicle in excess of regulatory limits - Paragraph 6).
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DETAILS 1.
Persons Contacted J. Ott, Chem-Nuclear Systems, Inc.
W. House, South Carolina DHEC R. Sappington, South Carolina DHEC H. Abercrombie, Browns Ferry Nuclear Plant (BFNP)
J. Harness, BFNP T. Chinn, BFNP A. Clement, BFNP S. Bugg, BFNP C. Cumming, BFNP D. Mims, BFNP 2.
General The NRC inspection consisted of a review of the shipping papers, radiation survey of the vehicle, 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 vehicles were inspected for appropriate marking, labeling, tightness of seals, integrity of package construction or any evidence of leakage.
Chem-Nuclear assigns a control number for each shipment upon arrival at the site. These numbers were called " shipment survey report numbers (SSR No.),
and were used by the inspectors to identify the licensee-shipper during this inspection.
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Shipments Inspected i
l This shipment was inspected at the Chem-Nuclear waste disposal site on April 28, 1980, and a continuation of the inspection made at Browns Ferry
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Nuclear Plant on May 1,1980.
4.
Shipping Papers
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l 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 49 CFR 172.100/172.200/172.202
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Material class 49 CFR 172.200/172.202
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Name sequence 49 CFR 172.200/172.202
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i Total quantity (Volume)
49 CFR 172.200/172.202
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Limited quantity 49 CFR 172.200/172.203
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Name of each radionuclide 49 CFR 172.203
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Physical and chemical form 49 CFR 172.203
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-2-Activity in curies 49 CFR 172.203
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Category or label 49 CFR 172.203
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Notation of NRC/ERDA package approval 49 CFR 172.203
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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 rhipping papers readily available for inspection and recognizable by authorities in case of accident.
No items of noncompliance were identified.
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 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 items of noncompliance were identified.
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 l
at the surface of the closed vehicle, in a vertical plane six feet from the sides of the vehicle where possible, and on the surface of a representative package.
Noncompliance: This shipment was carried by Tri-State hotor Transport on trailer number 440264. The shipment arrived at the disposal site on April 25,
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1980. Radiation levels of 600 mr/hr were measured at the surface of the trailer upon arrival. This exceeds the 200 mr/hr limit of 49 CFR 173.393(j)(2).
Further investigation showed that the high levels, apparently due to material contained in drum number D-16, were not detected by the licensee during vehic-ular surveys required by 49 CFR 173.393(n)(9). (80-21-01)
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Packaging i
A representative sampling of packages from the shipment 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
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Tight packages - ltd. Qty 49 CFR 173.391 or 173.392
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No release of material 49 CFR 173.392/173.393
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Radioactive material markings 49 CFR 172.310
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Security seals 49 CFR 173.393
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Gross weight requirements 49 CFR 172.310
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Proper shipping name
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49 CFR 172.100 LSA labeling 49 CFR 173.392
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j Cask design specifications 49 CFR 173.38
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i No items of noncompliance were identified.
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