ML19305C473
| ML19305C473 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 01/31/1980 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19305C453 | List: |
| References | |
| 50-219-79-23, NUDOCS 8003280638 | |
| Download: ML19305C473 (3) | |
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APPENDIX A NOTICE OF VIOLATION Jersey Central Power and Light Company Docket No. 50-219 Based on the results of an NRC inspection conducted on December 9-14, 18-19, 1979 and January 4,1980, it appears that certain of your activities were not conducted in full compliance with NRC regulations as indicated below.
Items A, B and C are Infractions.
Item D is a Deficiency.
A.
10 CFR 20.201, " Surveys", states in paragraph (b) that "each licensee shall l
make or cause to be made such surveys as may be necessary for him to comply with the regulations in this part."
Paragraph (a) of 20.201 defines
" surveys" as "an evaluation of the radiation hazards incident to the pro-duction, use, release, disposal or presence of radioactive materials..."
10 CFR 20.301, " Waste Disposal", general requirements, specifies that no licensee shall dispose of licensed material except by transfer to an authorized recipient as provided in 10 CFR 30...
10 CFR 30.41, " Transfer of byproduct material" requires that no licensee shall transfer byproduct material except as authorized pursuant to this section.
This section per-mits transfer to persons authorized to receive byproduct material under terms of a license issued by an Agreement State.
Chem Nuclear. Systems, Inc. 's Agreement State License for the Barnwell, South Carolina burial site (South Carolina Radioactive Material License No.
097) specifies in license condition 25 that solidified radioactive waste having detectable free standing liquids will not be permitted to be received by the burial site. South Carolina has defined "no detectable free standing liquid" as less than 1.0% liquid by volume.
Contrary to the above, no surveys were performed to determine the amount, if any, of free standing liquid in a shipment of dewatered resins (Shipment No. OC-1148-79) shipped by the licensee to the burial site on December 10, 1979.
Notwithstanding, the above shipment, no documentation was available to indicate previous shipments of solidified waste had been surveyed with respect to the above.
10 CFR 71.3, " Requirement for License," re B.
to the regulations in this part shall (a) quires that no licensee subject deliver any licensed materials to a carrier for transport or (b) transport licensed material except as authorized in a general license or specific license issued by the Commission, or as exempted in this part.
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APPENDIX A 2
Contrary to the above, on December 10, 1979, and at other times, shipments of licensed materials in excess of a Type A quantity were delivered to a carrier for transport without a general or specific license and no exemption in 10 CFR 71 was applicable.
C.
10 CFR 50, Domestic Licensing of Production and Utilization Facilities, Section 50.59, Changes, Tests and Experiments, specifies in paragraph (a) that the holder of a license authorizing operation of a utilization facility may make changes in the facility as described in the safety analysis repert, without prior Comission approval, unless the proposed change involves a change in the technical specifications incorporated in the license or an unreviewed safety question. Additionally,10 CFR 50.59(c) specifies that the holder of a license authorizing operation of a utilization facility who desires to make a change in technical specification or a change in the facility as described in the safety analysis report shall submit an appli-cation for amendment of his license.
Contrary to the above, as of December 10, 1979. no application for amend-ment to the facility license had been made which addressed changes to the facility technical specifications in order to include radioactive effluent releases from the new Radwaste Building.
lhis building, constructed and placed into operation by the licensee conscituted a change in the facility as described in the safety analysis report. The licensee had submitted a safety analysis report pursuant to 10 CFR 50.59(b) and proposed technical specificai; ions for building settlement in soil.
However, since initial introduction of radioactive material into this building in October 1978, no submittal has been made addressing the above releases.
D.
10 CFR 71.62. " Records," requires in part that the licensee shall maintain for a period of 2 years after its generation, a record of each shipment of more than a Type A quantity of radioactive material as defined in 71.4(g).
in a single package, showing where applicable, the results of the determi-nations required by 71.54, " Routine Determinations." These determinations include determinations that:
(a) the packaging has not been s gnificantly damaged... (c) the closure of the package and any sealing gaskets are pre-sent and are free from defects... and (1) the package has been loaded and closed in accordance with written procedures. Additionally, 71.62 requires records to be maintained of the results of determinations made pursuant to 10 CFR 71.53 including:
detenninations that there are no cracks, voids or other defects which could reduce the effectiveness of the packaging prior to its first use.
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1 APPENDIX A 3
Contrary to the above, the following shipments contained greater than a Type A quantity of radioactive material in a single package and were shipped from the licensee's facility without record of the above deter-minations being performed:
Date*
Shipment No.
Curie Content
- 3hTiped OC-1018-79 17.78 1/30/79 0C-1025-79 8.65 2/21/79 OC-1009-79 77.56 2/14/79 OC-1073-79 35.34 7/23/79
- Transport Group III Type A Limit 3 Curies.
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