ML19270H886
| ML19270H886 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Hatch, Monticello, Peach Bottom, Oconee, Oyster Creek, Pilgrim, Arkansas Nuclear, Vermont Yankee, Cook, Big Rock Point, FitzPatrick, BWX Technologies, 02700047, 07001193, Wood River Junction |
| Issue date: | 11/13/1979 |
| From: | Potter J, Woodruff R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | CHEM-NUCLEAR SYSTEMS, INC. |
| Shared Package | |
| ML19270H843 | List: |
| References | |
| 15000039-79-03A, 15000039-79-3A, 79-3A, NUDOCS 8001040224 | |
| Download: ML19270H886 (4) | |
Text
e UNITED STATES 8' E
'n NUCLEAR REGULATORY COMMISSION E
REGION 11 b[
o 101 MARtETTA ST., N.W., SUITE 3100 o
ATLANTA, G EORGIA 30303 Special Report: WASTE PACKAGING INSPECTIONS OF LICENSEE-SHIPPERS REPORT NO.79-03A
Reference:
...mo. Leo B. Higginbotham, A/D, Division of FFMSI to J. T. Sutherland, Chief, FFMS Branch, Region II Licensee-Shipper:
See Attachment A Disposal Site:
Chem-Nuclear Sys ems, Inc.
P. O. Box 726, Barnwell, South Carolina 29812 Docket No. J5000039 Inspector:
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Richard L. Woodruff, adiattbn Specialist, Date Signed FF&MS ct' 1S Branch Approved by:
,/f/7 J.
Potter, Chief, FF&MS Section, FF&MS Branch Date Signed
SUMMARY
Inspection Dates: October 17, and 18, 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 contamination; (5) DOT marking and labeling requirements for packages; and (6) DOT and NRC requirements for package external features.
Results: Of the six areas inspected involving 23 shipments, no items of noncom-pliance were identified.
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DETAILS 1.
Persons Contacted Michael F. Tkacik, South Carolina Department of Health James S. Itamura, U.S. Department of Transportation David Ebanhack, Health Physicist, Chem-Nuclear, Inc.
Stewart Corbett, Manager, Licensing and Safety, Chem-Nuclear, Inc.
Dan Taylor, Laboratory Supervisor, Chem-Nuclear, Inc.
Jim Shuler, Health Physics Supervisor, Chem-Nuclear, 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 Twenty-three shipments were inspected during the period of October 17 and 18, 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 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 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
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Category or label 49 CFR 172.203 Notation of NRC/ERDA package approval 49 CFR 172.203 Proper certification 49 CFR 172.20
e.
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 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 cask were surveyed at the surface.
No levels were in noncompliance with 49 CFR 173.393 limits.
7.
Con + amination 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 exami.ned 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
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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 173.38 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 items of noncompliance were noted.
10.
Interviews Upon arrival at the Barnwell site, the inspector checked in with the securiti:
guards, then went directly to the Health Physics office to inform site per-sonnel of my visit. I informed them that State and DOT Representatives would.
probably arrive at any time and that we would be inspecting shipments prior T o their entry into the controlled area.
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