ML19323G171
| ML19323G171 | |
| Person / Time | |
|---|---|
| Site: | 02700047, Oconee |
| Issue date: | 03/10/1980 |
| From: | Brown R, Potter J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | DUKE POWER CO. |
| Shared Package | |
| ML19323G151 | List: |
| References | |
| 15000039-80-02B, 15000039-80-2B, NUDOCS 8005300495 | |
| Download: ML19323G171 (4) | |
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UNITED STATES l'
'n NUCLEAR REGULATORY COMMISSION E
REGION 11 o
101 MARIETTA ST., N.W., SulTE 3100 o
ATLANTA, GEORGIA 30303 Special Report No. 15000039/80-02B (Waste Packaging Inspection)
Licensee / Shipper: Duke Power Company 422 S. Church Street Charlotte, NC 28242 Facility Name: Oconee Nuclear Station License Nos. DPR-38, DPR-47, DPR-55 Int.pection at Ch m W. le Ss s
Inc. Waste Burial Site at Barnwel, S Inspector:[
22[
R. t.. Bro
,' Radiation Specialist, Date Signed FF&MS ec i S Branch Approved by:
8d O
J. P(fotter, Chief, FF&MS Section, FF&MS Branch tatt Signed
SUMMARY
Inspection Dates: February 6, 1980 visit to Chem-Nuclear Waste disposal site, Barnwell, South Carolina for unan,nounced inspections of licensee-shippers.
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Areas Reviewed: Each licensee-shipper vehicle was inspected for compliance with Department of Transportation (DOT) and Nuclear Regulatory Commission (NRC) regu-lations as follows: (1) shipping paper requirements; (2) DOT Placarding require-ments; (3) radiation levels; (4) removable contamination; (5) DOT marking and labeling requirements for packages; (6) DOT and NRC requirements for external package features, and (7) prohibited articles or contents.
Results: Of the seven areas inspected involving this shipment, apparent items of noncompliance were identified in two areas.
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DETAILS 1.
Persons Contacted R. Sappington, South Carolina DHEC 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 observatians 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 licetsee-shippers during this inspection.
3.
Shipments Inspected This shipment was inspected on February 6,1980.
It was shipped from Oconee on 2/5/80 via Tri-State Motor Transport, Trailer No. 003, Freight Bill No.
334684, Shipper No. 80-595-I.
Shipment consisted of 150 drums.
4.
Shipping Papers The shipping papers were reviewed for completeness and to ascertain if the cortents 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 Mame 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 package approval 49 CFR 172.203 Proper certification 49 CFR 172.204 l
l
r 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)
Noncompliance: Drums were not braced to prevent shifting.
6.
Maximum Radiation Levels Each truck was surveyed for maximum radiation levels in the normally oc'cupied 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.
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 (LLA) packaging 49 CFR 173.392 Tight packages - Itd. Qty.,
49 CFR 173.391 or 173.392 No release of material 49 CrP 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
r Noncompliance: Drums were not labelled " Radioactive - LSA".
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.
Exit Interview The licensee was notified of the results of this inspection by telephone on March 4, 1980. The inspector contacted Mr. Rick Bond, Technical Services Supervisor for Oconee Nuclear Station.
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