ML19270H727
| ML19270H727 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs, Browns Ferry, Prairie Island, Brunswick, Duane Arnold, 05000054, 02700047, Barnwell |
| Issue date: | 11/19/1979 |
| From: | Brown R, Potter J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | TENNESSEE VALLEY AUTHORITY |
| Shared Package | |
| ML19270H724 | List: |
| References | |
| 15000039-79-04A, 15000039-79-4A, NUDOCS 8001020707 | |
| Download: ML19270H727 (5) | |
Text
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UNITED STATES 8')
~~ 'n NUCLEAR REGULATORY COMMISSION KEGION 11 h
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101 MARIETTA ST., N.W., SUITE 3100 0,
%*****o ATLANTA, GEORGIA 30303 Special Report: WASTE PACKAGING INSPECTIONS OF LICENSEE-SHIPPERS REPORT NO.79-04A
Reference:
Memo. Leo B. Higginbotham, A/D, Division of FFMSI to J. T. Sutherland, Chief, FFMS Branch Region II Licensee-Shipper:
See Address List Disposal Site:
Chem-Nuclear Systens, Inc.
P. O. Box 726 Bar ell, South Carolina 29812 tet N 039
/- Mgw M /f Inspector:*
R. A. Browlt, R.
iat o pecialist, Date Signed FF&MS c
,F>
nch Approved by:
k /f /i/]
J. P otter,' Chief, FF6MS Section, Date Signed I
.!S Branch
SUMMARY
Inspection Dates: October 31, 1979, 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) regula-tions as follows:
(1) shipping paper requirements; (2) DOT Placarding requirements; (3) radiation levels; (4) removable contaminations; (5) DOT marking and labeling requirements for packages; and (6) DOT ar' NRC requirements for package external features.
Results:
Of the six areas inspected involving this shipment, no apparent items of noncompliance were identified.
1674 257
]dh 800102,0
Inspection Report No. 15000039/79-04A DETAILS 1.
Persons Contacted W. House, South Carolina Department of Health S. Finklea, South Carolina Department of Health W. Barrow, U.S. Department of Transportation D. Ebenhack, Chem-Nuclear Systems, Inc.
J. Shuler, Chem-Nuclear Systems, Inc.
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 deter mine 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.
3.
Shipments Inspected Eleven (11) shipments were inspected during the period of October 29, and 31, 1979. A listing of the shippers inspected and their assigned SSR number is included as Attachment A.
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 notifica-tion procadures 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 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 Limited quantity 49 CFR 172.200/172.203 Name of each radionuclide 49 CFR 172.203 Physical and chemical form 49 CFR 172.203 Activity in curies 49 CFR 172.203 Category or label 49 CFR 172.203 Notation of NRC/ERDA 1674 258 package approval 49 CFR 172.203 Proper certification 49 CFR 172.20 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 accident.
No items of noncompliance were identified.
5.
Each vehicle was inspected for conformance with DOT placarding requirements (49 CFR 172, Subpart F and 49 CFR 173.392). The vehicles were 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 items of noncompliance were identified.
6.
Maximum Radiation Levels Each truck 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 sur-face 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 cask were surveyed at the surface.
No levels were in noncompliance with 49 CFR 173.393 limits.
7.
Contamination Smears Each vehicle and a representative sample package was surveyed for removable contamination by smearing over a 300 square centimeters area of the surface.
No more than two smears were taken from any package or vehicle. Smears were taken from areas that would most likely be contaminated. The smears were checked for gross Beta-gamma contamination at the site.
No smears were found to be contaminated in excess of 49 CFR 173.397 limits.
8.
Packaging A representative sampling of packages from each shipment was examined for conformance with DOT marking and labeling requirements. External features of the packages were examined for conformance with DOT and NRC requirments as noted below:
Low specific activity (LSA) packaging 49 CFR 173.392 Tight packages - Itd. 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 1674 259
Proper shipping name 49 CFR 172.100/172.300 LSA labeling 49 CFR 173.392 Cask design specifications 49 CFR 173.38 No items of noncompliance were identified.
9.
Verification of Package Contents Due to the lack of facilities for properly opening packages at the site, the criteria for opening packages was restricted to those packages containing solidified waste (to verify the absence of free-standing water) and/or where there was evidence of leakage.
No packages were selected for opening. South Carolina officials were present and concurred in the opening of the packages.
No items of noncompliance were noted.
1674 2c0
ATTACHMENT A
SUBJECT:
Address List
REFERENCE:
Waste Packaging Inspections, Report 79-04A OSR#
SHIPPER 017323 Tennessee Valley Authority 500A Chestnut Street Tower II Chattanooga, Tennessee 37401 Docket No. 50-259 017318 Knolls Atomic Power Lab Schenectady, New York Iowa Electric Light and Power IE Towers, P. O. Bcx 351 Cedar Rapids, Iowa 52406 Docket No. 50331 017320 Baltimore Gas and Electric Company Calvert Cliffs Plant Gas and Electric Building Baltimore, Maryland 21203 Docket No. 50-317 017297 Northern States Power Company 414 Nicollet Mall, 8th Floor Minneapolis, Minnesota 55401 Docket No. 50-282 017296 Allied General Nuclear Services Barnwell, South Carolina Docket No. 50-332 017295 Westinghouse Electric Corporation 017293 Columbia, South Carolina 017294 License No. 46-13530-01 017292 Carolina Power and Light Company P. O. Box 458 Southport, North Carolina Docket No. 50-325 017321 Westinghouse Electric Corporation Bettis Atomic Power Lab P. O. Box 79 West Mifflin, Pennsylvania Union Carbide Tuxedo, New York Docket No. 50-54 1674 241