ML19309F009
| ML19309F009 | |
| Person / Time | |
|---|---|
| Site: | 02700047, Pilgrim |
| Issue date: | 12/21/1979 |
| From: | Brown R, Potter J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | BOSTON EDISON CO. |
| Shared Package | |
| ML19309E999 | List: |
| References | |
| 15000039-79-08B, 15000039-79-8B, NUDOCS 8004280310 | |
| Download: ML19309F009 (3) | |
Text
1~4 UNITED STATES
.8 NUCLEAR REGULATORY COMMISSION o
Oa 8
accion i' e
101 MARIETTA ST., N.W., SUITE 3100 o
ATLANTA, GEORGIA 30303 Special Report: WASTE PACKAGING INSPECTIONS OF LICENSEE-SHIPPERS REPORT NO.79-08B
Reference:
Memo. Leo B. Higginbotham, A/D, Division of FFMSI to J. T. Sutherland, Chief, FFMS Branch, Region II Licensee-Shipper:
Boston Edison Company Pilgrim Plant Disposal Site:
Chem-Nuclear Systems, Inc.
P. O. pox 726, Barnwell, South Carolina 29812 D
N. 1 000 Inspector:
6A M. ~
2/
R. A.'Broda, R di ion Specialist, Date Signed FF&MS Se :
{ M S Branch
(#p
/MN N Approved by:
J. P otter, Chief, FF&MS Section, FF&MS Branch ITate ' Signed
SUMMARY
Inspection Dates:
December 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) 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; and (6) DOT and NRC requirements for package external features.
Results:
Of the six (6) areas inspected involving one shipment, one item of noncompliance was identified. (Radiation levels in excess of the limits speci-fied in 49 CFR 173.393(J)(3)).
8 004280 g \\ D J
s DETAILS
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Persons Contacted 4
J. Ott, Chem-Nuclear Systems, Inc.
V. Autry, South Carolina Department of Health and Environmental Control V. Stagliola, Boston Edison Company A. Trudeau, Boston Edison Company i
2.
General The NRC inspection consisted of a review of the shi'pping 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 1
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-six (26) shipments were inspected during the' period of December 18-19, 1979.
4.
Shipping Papers The shipping papers were ;eviewed for completeness and to ascertain if the contents of the shipmer'. 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:
daterial 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 l
Physical and chemical form 249 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 172.20 s
a.
, 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 coepliance 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 surw r (49 CFR 177.843)
No items of noncomplir.nce 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. Radiation levels of 17 mr/hr were measured at six feet from the vehicle surface.
7.
Packag:.ng A representative sampling of packages from each shipment was examined for j
conformance with DOT marking and labeling requirements. External features of the packages were examiaed for conformance with DOT and NRC requirments as noted below:
Low specific activity (LSA) packaging 49 CFR 173.392 Tight packages - ltd. Qty.,
- 49 CFR 173.391 or 173.392 No release of material 49 CFR 173.392/173.393 Radioactive caterial 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 C,FR 173.38 No items of noncompliaace were identified.
8.
Verification of Package Contents Due to the lack of facilities for properly opening packages at the site, the criteria for opening packages was rastricted to those packages containing solidified waste (to verify the absence of free-standing water) and/or where there was evidence of leakage.'
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No items of noncomp?.iance were noted.
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